工学博士, 北海道大学

Energy Engineering, Nuclear engineering

Bachelor's degree program, School of Engineering

Master's degree program, Graduate School of Engineering

Doctoral (PhD) degree program, Graduate School of Engineering

Mar. 2022, 日本原子力学会, 技術賞特賞
山本章夫;多田健一;千葉 豪

Mar. 2012, 日本原子力学会, 技術賞特賞
岩本修;柴田恵一;千葉豪

Sep. 2011, 日本原子力学会炉物理部会, 炉物理部会賞
千葉豪

Sep. 2006, 日本原子力学会核データ部会, 核データ部会奨励賞
千葉豪

Development of quick neutron spectrum reconstruction module based on POD for burnup calculation of fast reactor
Naoto AIZAWA; Tomoaki WATANABE; Go CHIBA; Kenichi TADA; Tatsuya FUJITA; Akio YAMAMOTO
Nuclear Engineering and Technology, 104176, 104176, Elsevier BV, Feb. 2026
Scientific journal

Burnup calculation using POD-based neutron spectrum reconstruction
Tomoaki Watanabe; Naoto Aizawa; Go Chiba; Kenichi Tada; Tatsuya Fujita; Akio Yamamoto
Journal of Nuclear Science and Technology, 63, 2, 166, 186, Informa UK Limited, 16 Sep. 2025
Scientific journal

Nuclear data sensitivity analysis on LWR nuclear fuel depletion with the modern evaluated nuclear data libraries
Hidayati Amar; Go Chiba; Tatsuya Fujita; Junshuang Fan; Yuya Inagaki
Journal of Nuclear Science and Technology, 1, 11, Informa UK Limited, 14 Apr. 2025, [Peer-reviewed]
Scientific journal

Nuclear education programs with reactor laboratory experiments at zero-powered research reactor facilities in Japan
Cheol Ho Pyeon; Tomohiro Endo; Go Chiba; Kenichi Watanabe; Genichiro Wakabayashi
Annals of Nuclear Energy, 204, 110531, 110531, Elsevier BV, Sep. 2024, [Peer-reviewed]
Scientific journal

Limited linear source approximation with Edge Detection for Convergence Stability of Method of Characteristics
Akio YAMAMOTO; Tomohiro ENDO; Go CHIBA
Journal of Nuclear Science and Technology, Informa UK Limited, 14 Apr. 2024, [Peer-reviewed]
Scientific journal

Computation time reduction of nuclear fuel burnup calculations with the predictor–corrector method using low-order model
Fuga Miyazawa; Go Chiba; Kosuke Tsujita; Shuhei Miwa
Annals of Nuclear Energy, 195, Jan. 2024, [Peer-reviewed]
Scientific journal

EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242
Riko Okuyama; Naohiko Otuka; Go Chiba; Osamu Iwamoto
Journal of Nuclear Science and Technology, 61, 1, 57, 67, Informa UK Limited, 27 Nov. 2023, [Peer-reviewed]
Scientific journal

Development of nuclear data processing code FRENDY version 2
Kenichi Tada; Akio Yamamoto; Satoshi Kunieda; Chikara Konno; Ryoichi Kondo; Tomohiro Endo; Go Chiba; Michitaka Ono; Masayuki Tojo
Journal of Nuclear Science and Technology, 61, 6, 830, 839, Informa UK Limited, 13 Nov. 2023, [Peer-reviewed]
Scientific journal

Reactor reactivity calculations with simplified-P₃ and perturbation theories
Jun-Shuang Fan; Go Chiba
Journal of Nuclear Science and Technology, Informa UK Limited, 07 Jul. 2023, [Peer-reviewed]
Scientific journal

Uncertainty quantification calculations of nuclide number densities of Gd-bearing fuel rods in light water reactors
Go Chiba
EPJ Web of Conferences, 281, 00016, 00016, EDP Sciences, 29 Mar. 2023, [Peer-reviewed]
Scientific journal, The Post-Irradiation Examination (PIE) data are quite useful to validate the evaluated nuclear data. Recently, a new experimental program, REGAL (the Rod-Extremity and Gadolinia AnaLysis), has been proposed and launched. During this program, the PIE data are acquired for the Gd-bearing fuel rods during (or after) the initial Gd burnout. These PIE data would be different from those for the normal UOX or MOX fuel rods from a viewpoint of nuclide transmutation process. In the present work, we attempt to quantify this difference through calculating sensitivity coefficients of nuclide number densities of the Gd-bearing rods using the depletion perturbation theory and performing uncertainty quantification calculations with the sensitivity coefficients and the nuclear data covariance data. Through the numerical analyses, we found that the impact of the uncertainties of the nuclear data of Gd isotopes on the number densities of actinoids is negligible. The nuclear data-induced uncertainties of Gd isotopes number densities are relatively large during the Gd depletion, and those become small after the Gd burnout. After the Gd burnout, the relative standard deviations of Gd-155 and -157 number densities are approximately 6% and 13%, respectively, and the nuclear data of the parent nuclides of these Gd isotopes, Gd-154 and -156, are also important as well as those of Gd-155 and -157.

Similarity evaluation between neutron multiplication factors and nuclide inventories during nuclear fuel burnup
Hiroki Harada; Go Chiba
EPJ Web of Conferences, 281, 00021, 00021, EDP Sciences, 29 Mar. 2023, [Peer-reviewed]
Scientific journal, There are several different types of the integral data of nuclear fission systems, and the accuracy of the numerical predictions of them are related with each other via the nuclear data commonly used in the numerical simulations. Thus, it is sometimes possible that measurement data of one type of the integral data are used to improve the prediction accuracy of the different type of the integral data. To quantitatively evaluate such possibility, the similarity of the different types of the integral data is important. In this study, we quantitatively evaluate the similarity between neutron multiplication factors and nuclide inventories during nuclear fuel burnup from the viewpoint of the nuclear data uncertainties using the representativity factors. Using the Burner module of the CBZ reactor physics code system for fuel pin-cell burnup problems, we calculated the sensitivity of the neutron infinite multiplication factors and the inventories of the 17 actinoids at several fuel burnup points. The neutron multiplication factor during the fuel burnup was considered the target parameter for which the prediction accuracy is improved, and the degree of similarity of the nuclide inventory data during burnup to the target was quantitatively evaluated using the representative factor. Subsequently, multiple nuclide inventory data were combined using the concept of the extended bias factor method to create a fictitious parameter, and we investigated how much this fictitious parameter can increase the representativity factor for the target parameter. As a result, the representativity factor for the target parameters could be increased to more than 0.8 using some nuclide inventory data, and up to 0.92 depending on the burnup, even taking into consideration the measurement error.

Japanese Evaluated Nuclear Data Library version 5: JENDL-5
Osamu Iwamoto; Nobuyuki Iwamoto; Satoshi Kunieda; Futoshi Minato; Shinsuke Nakayama; Yutaka Abe; Kohsuke Tsubakihara; Shin Okumura; Chikako Ishizuka; Tadashi Yoshida; Satoshi Chiba; Naohiko Otuka; Jean-Christophe Sublet; Hiroki Iwamoto; Kazuyoshi Yamamoto; Yasunobu Nagaya; Kenichi Tada; Chikara Konno; Norihiro Matsuda; Kenji Yokoyama; Hiroshi Taninaka; Akito Oizumi; Masahiro Fukushima; Shoichiro Okita; Go Chiba; Satoshi Sato; Masayuki Ohta; Saerom Kwon
Journal of Nuclear Science and Technology, 03 Feb. 2023, [Peer-reviewed]
English, Scientific journal

ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations
Go Chiba; Akio Yamamoto; Kenichi Tada
Journal of Nuclear Science and Technology, 60, 2, 132, 139, 2023, [Peer-reviewed]
Scientific journal

Validation of LWR fuel depletion calculation module of reactor physics code system CBZ
Go Chiba; Hiroki Harada
Journal of Nuclear Science and Technology, 60, 8, 969, 979, 2023, [Peer-reviewed]
Scientific journal

Level swell analysis of stagnant water pool in filtered containment venting systems
Yasunori Yamamoto; Naoto Kitahara; Fuga Miyazawa; Go Chiba; Shuichiro Miwa; Michitsugu Mori
Progress in Nuclear Energy, 155, Jan. 2023, [Peer-reviewed]
Scientific journal

Improvement and benchmarking of the deterministic transport calculation code CBZ to design beam shaping assembly for BNCT
Go Chiba; Hikaru Handa; Masayori Ishikawa
Applied Radiation and Isotopes, 190, 110465, 110465, Elsevier BV, Dec. 2022, [Peer-reviewed]
Scientific journal

Implementation of Resonance Up-scattering Treatment in FRENDY Nuclear Data Processing System
Akio Yamamoto; Tomohiro Endo; Go Chiba; Kenichi Tada
Nuclear Science and Engineering, 1, 13, Informa UK Limited, 21 Jul. 2022, [Peer-reviewed]
Scientific journal

Enhancement of applicability of high-efficiency random sampling method using control variates method and sensitivity coefficients
Takumi Kida; Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 59, 7, 866, 874, Jul. 2022, [Peer-reviewed]
English, Scientific journal

Experimental analysis of small sample reactivity measured in the SEG experiment by a deterministic reactor physics code system CBZ
Go Chiba; Junshuang Fan
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 59, 2, 247, 256, Feb. 2022, [Peer-reviewed]
English, Scientific journal

Development and verification of fast reactor burnup calculation module FRBurner in code system CBZ
Junshuang Fan; Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 58, 12, 1269, 1287, Jun. 2021, [Peer-reviewed]
English, Scientific journal

Improvement of the optimally-weighted predictor-corrector method for nuclear fuel burnup calculations
Jumpei Sasuga; Go Chiba; Yasunori Ohoka; Kento Yamamoto; Yasuhiro Kodama; Hiroaki Nagano
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, Jun. 2021, [Peer-reviewed]
English, Scientific journal

Multi-group neutron cross section generation capability for FRENDY nuclear data processing code
Akio Yamamoto; Kenichi Tada; Go Chiba; Tomohiro Endo
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, Jun. 2021, [Peer-reviewed]
English, Scientific journal

Sensitivity of the neutron multiplication factor to gadolinium isotopes' nuclear data for light water reactor fuel assemblies in the peak reactivity burnup range
Go Chiba
ANNALS OF NUCLEAR ENERGY, 151, Feb. 2021, [Peer-reviewed]
English, Scientific journal

Sensitivity and uncertainty analyses of fission product nuclide inventories for passive gamma spectroscopy
Go Chiba; Keisuke Honta
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 57, 12, 1265, 1275, Dec. 2020, [Peer-reviewed]
English, Scientific journal

A comparative study of the delta-Eddington and Galerkin quadrature methods for highly forward scattering of photons in random media
Hiroyuki Fujii; Go Chiba; Yukio Yamada; Yoko Hoshi; Kazumichi Kobayashi; Masao Watanabe
JOURNAL OF COMPUTATIONAL PHYSICS, 423, Dec. 2020, [Peer-reviewed]
English, Scientific journal

Quantification of integral data effectiveness using the concept of active subspace in evaluated nuclear data validation
Go Chiba; Daichi Imazato
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 57, 11, 1245, 1255, Nov. 2020, [Peer-reviewed]
English, Scientific journal

Neutron Generation Time in Highly-Enriched Uranium Core at Kyoto University Critical Assembly
Cheol Ho Pyeon; Masao Yamanaka; Tomohiro Endo; Go Chiba; Willem F. G Van Rooijen; Kenichi Watanabe
Nuclear Science and Engineering, 194, 12, 1, 12, Informa UK Limited, 07 Jul. 2020, [Peer-reviewed]
Scientific journal

Numerical benchmark problem of solid-moderated enriched-uranium-loaded core at Kyoto university critical assembly
Go Chiba; Tomohiro Endo
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 57, 2, 187, 195, Feb. 2020, [Peer-reviewed]
English, Scientific journal

Nuclear data-induced uncertainty quantification of prompt neutron decay constant based on perturbation theory for ADS experiments at KUCA
Tomohiro Endo; Kenichi Watanabe; Go Chiba; Masao Yamanaka; Willem Frederik Geert van Rooijen; Cheol Ho Pyeon
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 57, 2, 196, 204, Feb. 2020, [Peer-reviewed]
English, Scientific journal

Spatially-dependent nuclear reactor kinetic calculations with the explicit fission product model
Katagiri Koji; Chiba Go
ANNALS OF NUCLEAR ENERGY, 133, 202, 208, Nov. 2019, [Peer-reviewed]

Experimental analyses of beta eff/? in accelerator-driven system at Kyoto University Critical Assembly
Yamanaka Masao; Pyeon Cheol Ho; Endo Tomohiro; Watanabe Kenichi; Chiba Go; van Rooijen Willem Frederik Geert
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 57, 2, 205, 215, 26 Sep. 2019, [Peer-reviewed]
Scientific journal

Numerical treatment of highly forward scattering on radiative transfer using the delta-M approximation and Galerkin quadrature method
Hiroyuki Fujii; Go Chiba; Yukio Yamada; Yoko Hoshi; Kazumichi Kobayashi; Masao Watanabe
Proceedings of the 9th International Symposium on Radiative Transfer, RAD-19, SM05, 261, 268, Sep. 2019, [Peer-reviewed]
English, International conference proceedings

First nuclear transmutation of Np-237 and Am-241 by accelerator-driven system at Kyoto University Critical Assembly
Pyeon Cheol Ho; Yamanaka Masao; Oizumi Akito; Fukushima Masahiro; Chiba Go; Watanabe Kenichi; Endo Tomohiro; Van Rooijen Wilfred G; Hashimoto Kengo; Sakon Atsushi; Aizawa Naoto; Kuriyama Yasutoshi; Uesugi Tomonori; Ishi Yoshihiro
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 56, 8, 684, 689, 03 Aug. 2019, [Peer-reviewed]
English, Scientific journal

Combination of sensitivity-based and random sampling-based methodologies for efficient uncertainty quantification calculations with control variates method
Nihira Shunsuke; Chiba Go
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 19 Jun. 2019, [Peer-reviewed]

Development of high efficiency multi-nuclide aerosol filters for radiation protection during a process of cutting core debris for Fukushima Daiich NPP
Tadashi Narabayashi; Go Chiba; Akinori Ishii; Yuta Watanabe; Naoto Kitahara; Kazuhiro Hirai; Takao Masuda; Yuta Nakasaka; Nobuaki Sato; Koji Endo; Toshiki Kobayashi
International Conference on Nuclear Engineering, Proceedings, ICONE, 2019-, American Society of Mechanical Engineers (ASME), 18 May 2019
English, International conference proceedings

Revisiting mini-max polynomial approximation method for nuclear fuel depletion calculation
Go Chiba; Yasunori Ohoka; Kento Yamamoto; Hiroaki Nagano
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, 2401, 2410, American Nuclear Society, 2019, [Peer-reviewed]
English, International conference proceedings

Accurate and efficient computation of the 3D radiative transfer equation in highly forward-peaked scattering media using a renormalization approach.
Array,Yukio Yamada; Go Chiba; Yoko Hoshi; Array; Masao Watanabe
J. Comput. Physics, 374, 591, 604, 01 Dec. 2018, [Peer-reviewed]

Uncertainty quantification works relevant to fission yields and decay data
Chiba Go; Nihira Shunsuke
EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 4, 14 Nov. 2018, [Peer-reviewed]

Uncertainty quantification of criticality in solid-moderated and -reflected cores at Kyoto University Critical Assembly
Cheol Ho Pyeon; Masao Yamanaka; Makoto Ito; Go Chiba; Tomohiro Endo; Song Hyun Kim; Willem Fredrik G. van Rooijen
Journal of Nuclear Science and Technology, 55, 7, 812, 821, 03 Jul. 2018, [Peer-reviewed]
English, Scientific journal

Research activities on nuclear reactor physics and thermal-hydraulics in Japan after Fukushima-Daiichi accident
Shuichiro Miwa; Yasunori Yamamoto; Go Chiba
Journal of Nuclear Science and Technology, 55, 6, 575, 598, 03 Jun. 2018, [Peer-reviewed]
English

Experimental analysis and uncertainty quantification using random sampling technique for ADS experiments at KUCA
Tomohiro Endo; Go Chiba; Willem Frederik Geert van Rooijen; Masao Yamanaka; Cheol Ho Pyeon
Journal of Nuclear Science and Technology, 55, 4, 450, 459, 03 Apr. 2018, [Peer-reviewed]
English, Scientific journal

Perturbation theory for nuclear fuel depletion calculations with predictor–corrector method
Go Chiba
Journal of Nuclear Science and Technology, 55, 3, 290, 300, 04 Mar. 2018, [Peer-reviewed]
English, Scientific journal

PRESSURE DEPENDENCE OF TWO PHASE FLOW BEHAVIOR OF STAGNANT WATER IN A VERTICAL PIPE DURING STEAM INJECTION
Naoto Kitahara; Yasunori Yamamoto; Tadashi Narabayashi; Go Chiba
PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 9, 2018
English, International conference proceedings

Uncertainty quantification of neutron multiplication factors of light water reactor fuels during depletion
Chiba Go; Okumura Shintaro
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 55, 9, 1043, 1053, 2018, [Peer-reviewed]

Effect of instructor’s actions and attitudes on student’s motivation and discussion process in TBL class for graduate students
Shotaro Imai; Ankit Ravankar; Michiyo Shimamura; Taichi Takasuka; Go Chiba; Yasuhiro Yamanaka
International Journal of Institutional Research and Management, 1, 2, 17, 35, Sep. 2017, [Peer-reviewed]
English, Scientific journal

Analysis of the KUCA ADS Benchmarks with Diffusion Theory
W. F. G. Rooijen; T. Endo; G. Chiba; C. H. Pyeon
Progress in Nuclear Energy, 101, 243, 250, Elsevier BV, Sep. 2017, [Peer-reviewed]
English, Scientific journal

Benchmarks of subcriticality in accelerator-driven system at Kyoto University Critical Assembly
Cheol Ho Pyeon; Masao Yamanaka; Song-Hyun Kim; Thanh-Mai Vu; Tomohiro Endo; Willem Fredrik G. Van Rooijen; Go Chiba
NUCLEAR ENGINEERING AND TECHNOLOGY, 49, 6, 1234, 1239, Sep. 2017, [Peer-reviewed]
English, Scientific journal

Experimental benchmarks on kinetic parameters in accelerator-driven system with 100 MeV protons at Kyoto University Critical Assembly
Cheol Ho Pyeon; Masao Yamanaka; Tomohiro Endo; Willem Fredrik G. van Rooijen; Go Chiba
ANNALS OF NUCLEAR ENERGY, 105, 346, 354, Jul. 2017, [Peer-reviewed]
English, Scientific journal

Problem-based Learning and Problem Finding Among University Graduate Students
Ankit A. Ravankar; Shotaro Imai; Michiyo Shimamura; Go Chiba; Taichi Takasuka
Journal of Higher Education and Lifelong Learning, 24, 9, 20, 北海道大学高等教育推進機構, Mar. 2017, [Peer-reviewed]
English, Scientific journal, In recent years, problem-based learning (PBL) techniques have been gaining momentum inschools and university curricula around the world. The main advantage of the PBL method is that it promotescreative problem solving, improves cognition and enhances overall thought processes in learners. For mostPBL-style programmes, problem solving is at the core, although the notion of problem discovery or problemfinding is not seriously considered. In most cases, students are always presented with a structured and welldefinedproblem, but have no experience of solving an ill-structured problem or ʻwicked' problem. Thepresent study focuses on problem finding as a critical step towards developing problem solving skills inuniversity graduate students. The study aims at understanding the importance of problem formulation andcreativity, and focuses as well on our attempt to teach problem finding as an important tool in thedevelopment of creative thinking and problem solving among graduate students. The study is part of a specialgraduate programme called the Nitobe School at Hokkaido University in Japan, which started in 2015. In anactive learning classroom setting, this course is intended to support graduate students in their discovery of illstructuredproblems, help them to understand their formulation and thereby improve their problem solvingskills. We present the results of our teaching method for the first year at the Nitobe School and share ourfindings through this work.

Consistent adjustment of radioactive decay and fission yields data with measurement data of decay heat and beta-delayed neutron activities
Go Chiba
ANNALS OF NUCLEAR ENERGY, 101, 23, 30, Mar. 2017, [Peer-reviewed]
English, Scientific journal

Feasibility study of decay heat uncertainty reduction using nuclear data adjustment method with experimental data
Yosuke Kawamoto; Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 54, 2, 213, 222, 2017, [Peer-reviewed]
English, Scientific journal

Development of a fuel depletion sensitivity calculation module for multi-cell problems in a deterministic reactor physics code system CBZ
Go Chiba; Yosuke Kawamoto; Tadashi Narabayashi
ANNALS OF NUCLEAR ENERGY, 96, 313, 323, Oct. 2016, [Peer-reviewed]
English, Scientific journal

Advanced Bondarenko method for resonance self-shielding calculations in deterministic reactor physics code system CBZ
Go Chiba; Tadashi Narabayashi
ANNALS OF NUCLEAR ENERGY, 96, 277, 286, Oct. 2016, [Peer-reviewed]
English, Scientific journal

Automatic construction of a simplified burn-up chain model by the singular value decomposition
Takanori Kajihara; Masashi Tsuji; Go Chiba; Yosuke Kawamoto; Yasunori Ohoka; Tadashi Ushio
ANNALS OF NUCLEAR ENERGY, 94, 742, 749, Aug. 2016, [Peer-reviewed]
English, Scientific journal

DEVELOPMENT OF HIGH EFFICIENCY CONTAINMENT VENTING SYSTEM BY USING AgX
Tadashi Narabayashi; Yuuhei Sugano; Hiroki Imaeda; Go Chiba; Nobuaki Sato; Koji Endo; Toshiki Kobayashi
PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 3, 2016, [Peer-reviewed]
English, International conference proceedings

Nuclear data-induced uncertainty quantification of neutronics parameters of accelerator-driven system
Go Chiba; Cheol Ho Pyeon; Wilfred van Rooijen; Tomohiro Endo
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 53, 10, 1653, 1661, 2016, [Peer-reviewed]
English, Scientific journal

Uncertainty quantification of total delayed neutron yields and time-dependent delayed neutron emission rates in frame of summation calculations
Go Chiba; Tadashi Narabayashi
ANNALS OF NUCLEAR ENERGY, 85, 846, 855, Nov. 2015, [Peer-reviewed]
English, Scientific journal

Important fission product nuclides identification method for simplified burnup chain construction
Go Chiba; Masashi Tsuji; Tadashi Narabayashi; Yasunori Ohoka; Tadashi Ushio
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 52, 7-8, 953, 960, Aug. 2015, [Peer-reviewed]
English, Scientific journal

Numerical solution of matrix exponential in burn-up equation using mini-max polynomial approximation
Yosuke Kawamoto; Go Chiba; Masashi Tsuji; Tadashi Narabayashi
ANNALS OF NUCLEAR ENERGY, 80, 219, 224, Jun. 2015, [Peer-reviewed]
English, Scientific journal

Accident analysis of fukushima daiichi nuclear power station unit 1
Masahide Kobayashi; Tadashi Narabayashi; Masashi Tuji; Go Chiba; Yasunori Nagata; Tomohiro Shimoe
Transactions of the Atomic Energy Society of Japan, 14, 1, 12, 24, Atomic Energy Society of Japan, 2015, [Peer-reviewed]
Japanese, Scientific journal

Variance Reduction Factor of Nuclear Data for Integral Neutronics Parameters
G. Chiba; M. Tsuji; T. Narabayashi
NUCLEAR DATA SHEETS, 123, 62, 67, Jan. 2015, [Peer-reviewed]
English, Scientific journal

Estimation of neutronics parameter sensitivity to nuclear data in random sampling-based uncertainty quantification calculations
Go Chiba; Yosuke Kawamoto; Masashi Tsuji; Tadashi Narabayashi
ANNALS OF NUCLEAR ENERGY, 75, 395, 403, Jan. 2015, [Peer-reviewed]
English, Scientific journal

RESONANCE SELF-SHIELDING EFFECT IN UNCERTAINTY QUANTIFICATION OF FISSION REACTOR NEUTRONICS PARAMETERS
Go Chiba; Masashi Tsuji; Tadashi Narabayashi
NUCLEAR ENGINEERING AND TECHNOLOGY, 46, 3, 281, 290, Jun. 2014, [Peer-reviewed]
English, Scientific journal

Photon transport effect on intra-subassembly thermal power distribution in fast reactor
Go Chiba; Masashi Tsuji; Tadashi Narabayashi
ANNALS OF NUCLEAR ENERGY, 65, 41, 46, Mar. 2014
English, Scientific journal

Nuclear data sensitivity analysis for isotopic generation using jendl-4.0, endf/b-vii.1 and jeff-3.1.1
Yosuke Kawamoto; Go Chiba; Masashi Tsuji; Tadashi Narabayashi
Proceedings of the International Conference on Physics of Reactors, PHYSOR 2014, Japan Atomic Energy Agency, JAEA, 2014
English, International conference proceedings

Recent activities in the field of reactor physics
Masahiro Tatsumi; Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 51, 9, 1161, 1163, 2014, [Peer-reviewed]
English

Sensitivity and uncertainty analysis for reactor stable period induced by positive reactivity using one-point adjoint kinetics equation
Go Chiba; Masashi Tsuji; Tadashi Narabayashi
Journal of Nuclear Science and Technology, 50, 12, 1150, 1160, 01 Dec. 2013
English, Scientific journal

Uncertainty quantification of neutronic parameters of light water reactor fuel cells with JENDL-4.0 covariance data
Go Chiba; Masashi Tsuji; Tadashi Narabayashi
Journal of Nuclear Science and Technology, 50, 7, 751, 760, 01 Jul. 2013
English, Scientific journal

Important fission product nuclides identification method for simplified burnup-chain construction
Go Chiba; Masashi Tsuji; Tadashi Narabayashi; Yasunori Ohoka; Tadashi Ushio
Transactions of the American Nuclear Society, 109, 2, 1299, 1300, American Nuclear Society, 2013
English, International conference proceedings

Efficient fission neutron spectrum matrix representation by singular value decomposition technique
Go Chiba; Akio Yamamoto; Masashi Tsuji; Tadashi Narabayashi
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 49, 7, 748, 753, Jul. 2012
English, Scientific journal

A note on application of superhomogeneisation factors to integro-differential neutron transport equations
Go Chiba; Masashi Tsuji; Ken-ichiro Sugiyama; Tadashi Narabayashi
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 49, 1-2, 272, 280, Jan. 2012
English, Scientific journal

JENDL-4.0 Benchmarking for Effective Delayed Neutron Fraction of Fast Neutron Systems
Go Chiba; Masashi Tsuji; Ken-ichiro Sugiyama; Tadashi Narabayashi
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48, 12, 1471, 1477, Dec. 2011
English, Scientific journal

JENDL-4.0 Benchmarking for Effective Delayed Neutron Fraction of Fast Neutron Systems
Go Chiba; Masashi Tsuji; Ken-ichiro Sugiyama; Tadashi Narabayashi
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48, 12, 1471, 1477, Dec. 2011, [Peer-reviewed]
English, Scientific journal

Benchmark Calculations of Sodium-Void Experiments with Uranium Fuels at the Fast Critical Assembly FCA
FUKUSHIMA MASAHIRO; KITAMURA YASUNORI; KUGO TERUHIKO; YAMANE TSUYOSHI; ANDOH MASAKI; CHIBA GO; ISHIKAWA MAKOTO; OKAJIMA SHIGEAKI
Prog Nucl Sci Technol (Web), 2, WEB ONLY 306-311, Oct. 2011
English

On Effective Delayed Neutron Fraction Calculations with Iterated Fission Probability
Go Chiba; Yasunobu Nagaya; Takamasa Mori
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48, 8, 1163, 1169, Aug. 2011
English, Scientific journal

JENDL-4.0 Integral Testing for Fission Systems
Keisuke Okumura; Kazuteru Sugino; Go Chiba; Yasunobu Nagaya; Kenji Yokoyama; Teruhiko Kugo; Makoto Ishikawa; Shigeaki Okajima
JOURNAL OF THE KOREAN PHYSICAL SOCIETY, 59, 2, 1135, 1140, Aug. 2011, [Peer-reviewed]
English, Scientific journal

Development of a Unified Cross-section Set ADJ2010 Based on Adjustment Technique for Fast Reactor Core Design
K. Sugino; M. Ishikawa; K. Yokoyama; Y. Nagaya; G. Chiba; T. Hazama; T. Kugo; K. Numata; T. Iwai; T. Jin
JOURNAL OF THE KOREAN PHYSICAL SOCIETY, 59, 2, 1357, 1360, Aug. 2011, [Peer-reviewed]
English, Scientific journal

On Effective Delayed Neutron Fraction Calculations with Iterated Fission Probability
Go Chiba; Yasunobu Nagaya; Takamasa Mori
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48, 8, 1163, 1169, Aug. 2011, [Peer-reviewed]
English, Scientific journal

Application of the hierarchical domain decomposition boundary element method to the simplified P-3 equation
Go Chiba
ANNALS OF NUCLEAR ENERGY, 38, 5, 1033, 1038, May 2011, [Peer-reviewed]
English, Scientific journal

JENDL-4.0 Benchmarking for Fission Reactor Applications
Go Chiba; Keisuke Okumura; Kazuteru Sugino; Yasunobu Nagaya; Kenji Yokoyama; Teruhiko Kugo; Makoto Ishikawa; Shigeaki Okajima
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48, 2, 172, 187, Feb. 2011, [Peer-reviewed]
English, Scientific journal

Improvement of Tone's Method with Two-Term Rational Approximation
Akio Yamamoto; Tomohiro Endo; Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 48, 2, 263, 271, Feb. 2011, [Peer-reviewed]
English, Scientific journal

Diffusion coefficients for LMFBR cells calculated with MOC and Monte Carlo methods
W. F. G. van Rooijen; G. Chiba
ANNALS OF NUCLEAR ENERGY, 38, 1, 133, 144, Jan. 2011, [Peer-reviewed]
English, Scientific journal

Comparison of Monte Carlo calculation methods for effective delayed neutron fraction
Yasunobu Nagaya; Go Chiba; Takamasa Mori; Dwi Irwanto; Ken Nakajima
ANNALS OF NUCLEAR ENERGY, 37, 10, 1308, 1315, Oct. 2010, [Peer-reviewed]
English, Scientific journal

Sensitivity Analysis of Fission Product Concentrations for Light Water Reactor Burned Fuel
Go Chiba; Keisuke Okumura; Akito Oizumi; Masaki Saito
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 47, 7, 652, 660, Jul. 2010
English, Scientific journal

Sensitivity Analysis of Fission Product Concentrations for Light Water Reactor Burned Fuel
Go Chiba; Keisuke Okumura; Akito Oizumi; Masaki Saito
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 47, 7, 652, 660, Jul. 2010, [Peer-reviewed]
English, Scientific journal

Neutronic calculations for steel-reflected fast critical systems with the sub-group Sn method
Go Chiba; Teruhiko Kugo
International Conference on the Physics of Reactors 2010, PHYSOR 2010, 2, 1064, 1074, American Nuclear Society, 2010
English, International conference proceedings

Evaluation of Neutron Nuclear Data on Arsenic-75 for JENDL-4
Keiichi Shibata; Go Chiba; Akira Ichihara; Satoshi Kunieda
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 47, 1, 40, 46, Jan. 2010
English, Scientific journal

Evaluation of Neutron Nuclear Data on Arsenic-75 for JENDL-4
Keiichi Shibata; Go Chiba; Akira Ichihara; Satoshi Kunieda
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 47, 1, 40, 46, Jan. 2010, [Peer-reviewed]
English, Scientific journal

Impact of Incident Energy Dependence of Prompt Fission Neutron Spectra on Uncertainty Analyses
Go Chiba; Yasunobu Nagaya
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 46, 10, 1000, 1003, Oct. 2009
English, Scientific journal

Impact of Incident Energy Dependence of Prompt Fission Neutron Spectra on Uncertainty Analyses
Go Chiba; Yasunobu Nagaya
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 46, 10, 1000, 1003, Oct. 2009, [Peer-reviewed]
English, Scientific journal

JENDL Actinoid File 2008
Osamu Iwamoto; Tsuneo Nakagawa; Naohiko Otuka; Satoshi Chiba; Keisuke Okumura; Go Chiba; Takaaki Ohsawa; Kazuyoshi Furutaka
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 46, 5, 510, 528, May 2009
English, Scientific journal

Evaluation of sensitivity coefficients of effective multiplication factor with respect to prompt fission neutron spectrum
Yasunobu Nagaya; Ivan Kodeli; Go Chiba; Makoto Ishikawa
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 603, 3, 485, 490, May 2009, [Peer-reviewed]
English, Scientific journal

Calculation of Effective Delayed Neutron Fraction Using a Modified k-Ratio Method
Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 46, 5, 399, 402, May 2009, [Peer-reviewed]
English, Scientific journal

JENDL Actinoid File 2008
Osamu Iwamoto; Tsuneo Nakagawa; Naohiko Otuka; Satoshi Chiba; Keisuke Okumura; Go Chiba; Takaaki Ohsawa; Kazuyoshi Furutaka
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 46, 5, 510, 528, May 2009, [Peer-reviewed]
English, Scientific journal

Calculation of effective delayed neutron fraction using a modified k-ratio method
Go Chiba
Journal of Nuclear Science and Technology, 46, 5, 399, 402, 2009
English, Scientific journal

JENDL actinoid file 2008 and plan of covariance evaluation
Iwamoto, Osamu; Nakagawa, Tsuneo; Otsuka, Naohiko; Chiba, Satoshi; Okumura, Keisuke; Chiba, Go
Nuclear Data Sheets, 109, 12, 2885, 2889, Dec. 2008, [Peer-reviewed]
English, JENDL Actinoid File 2008 (JENDL/AC-2008) was released in March 2008. It provides nuclear data of neutron induced nuclear reactions for actinoid nuclides from Ac to Fm. The data for 62 nuclides in JENDL-3.3 were revised and newly evaluated data for 17 nuclides, which have a half-life longer than 1 day, were added. Nuclear reaction model code CCONE was widely used for the evaluations of cross sections and energy-angular distributions of secondary neutrons in fast energy region. Covariance data for the fission and capture cross sections and the number of neutrons per fission will be evaluated for important nuclides in the JENDL/AC-2008. The evaluation methods and the results will be presented and the plan of the covariance evaluations also will be mentioned.

Development of JENDL actinoid file
Iwamoto, Osamu; Nakagawa, Tsuneo; Otsuka, Naohiko; Chiba, Satoshi; Okumura, Keisuke; Chiba, Go
Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 8, Sep. 2008
English, Nuclear data for neutron induced reactions with actinides from Ac to Fm have been evaluated for JENDL Actinoid File (JENDL/AC). Almost all data in JENDL-3.3 have been updated based on available experimental data and using the newly developed theoretical model code CCONE. Integral benchmark tests for fission reactors are in progress using preliminary versions of JENDL/AC. The JENDL/AC will be released in 2008.

Covariance analyses of self-shielding factor and its temperature gradient for uranium-238 neutron capture reaction
Naohiko Otuka; Atsushi Zukeran; Hideki Takano; Go Chiba; Makoto Ishikawa
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 45, 3, 195, 210, Mar. 2008, [Peer-reviewed]
English, Scientific journal

MARBLE: A next generation neutronics analysis code system for fast reactors
Kenji Yokoyama; Yasushi Hirai; Masahiro Tatsumi; Hideaki Hyoudou; Go Chiba; Taira Hazama; Yasunobu Nagaya; Makoto Ishikawa
International Conference on the Physics of Reactors 2008, PHYSOR 08, 3, 2315, 2322, Paul Scherrer Institut, 2008
English, International conference proceedings

Sodium void reactivity worth calculations for fast critical assemblies without whole-lattice homogenization
Go Chiba; Yoichiro Shimazu
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 44, 12, 1526, 1534, Dec. 2007, [Peer-reviewed]
English, Scientific journal

Neutron transport benchmark problem proposal for fast critical assembly without homogenizations
Go Chiba; Kazuyuki Numata
ANNALS OF NUCLEAR ENERGY, 34, 6, 443, 448, Jun. 2007, [Peer-reviewed]
English, Scientific journal

Verification of homogenization in fast critical assembly analyses
Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 43, 11, 1395, 1405, Nov. 2006, [Peer-reviewed]
English, Scientific journal

Improvement of moment-based probability table for resonance self-shielding calculation
Go Chiba; Hironobu Unesaki
ANNALS OF NUCLEAR ENERGY, 33, 13, 1141, 1146, Sep. 2006, [Peer-reviewed]
English, Scientific journal

Overestimation in parallel component of neutron leakage observed in sodium void reactivity worth calculation for fast critical assemblies
Go Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 43, 8, 946, 949, Aug. 2006, [Peer-reviewed]
English, Scientific journal

Development of a fine and ultra-fine group cell calculation code SLAROM-UF for fast reactor analyses
Taira Hazama; Go Chiba; Kazuteru Sugino
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 43, 8, 908, 918, Aug. 2006, [Peer-reviewed]
English, Scientific journal

Revision and application of the covariance data processing code, ERRORJ
Go Chiba; Makoto Ishikawa
AIP Conference Proceedings, 769, 468, 471, 24 May 2005, [Peer-reviewed]
English, International conference proceedings

Criticality analyses for fast neutron systems sensitive to iron
Go Chiba
Transactions of the Atomic Energy Society of Japan, 4, 1, 66, 76, Atomic Energy Society of Japan, 2005
Japanese, Scientific journal

JOYO MK-III performance test at low power and its analysis
Gou Chiba; Kenji Yokoyama; Shigetaka Maeda; Takashi Sekine
Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, 263, 273, Dec. 2004, [Peer-reviewed]
English, International conference proceedings

高速炉炉心解析における中性子非等方散乱と実効断面積の中性子束角度依存性の取扱いの臨界性への効果
千葉豪
日本原子力学会和文論文誌, 3, 2, 200, 207, 25 Jun. 2004
Japanese

Effect of neutron anisotropie scattering and treatment of angular dependency of neutron flux in effective cross section on criticality in fast reactor analysis
Gou Chiba
Transactions of the Atomic Energy Society of Japan, 3, 2, 200, 207, Atomic Energy Society of Japan, 2004
Japanese, Scientific journal

A combined method to evaluate the resonance self shielding effect in power fast reactor fuel assembly calculation
G Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 40, 7, 537, 543, Jul. 2003, [Peer-reviewed]
English, Scientific journal

The revision of nuclear constant set for fast reactor, JFS-3-J3.2
Gou Chiba; Taira Hazama; Makoto Ishikawa
Transactions of the Atomic Energy Society of Japan, 1, 4, 335, 340, 2002
English, Scientific journal

Development of the hierarchical domain decomposition boundary element method for solving the three-dimensional multiregion neutron diffusion equations
G Chiba; M Tsuji; Y Shimazu
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 38, 8, 664, 673, Aug. 2001, [Peer-reviewed]
English, Scientific journal

A hierarchical domain decomposition boundary element method with a higher order polynomial expansion for solving 2-D multiregion neutron diffusion equations
G Chiba; M Tsuji; Y Shimazu
ANNALS OF NUCLEAR ENERGY, 28, 9, 895, 912, Jun. 2001, [Peer-reviewed]
English, Scientific journal

High-speed parallel solution of the neutron diffusion equation with the hierarchical domain decomposition boundary element method incorporating parallel communications
M Tsuji; G Chiba
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 37, 5, 477, 485, May 2000, [Peer-reviewed]
English, Scientific journal

FRENDY/MG: a multi-group cross section generation module using ace pointwise cross sections
Akio Yamamoto; Tomohiro Endo; Basma Foad; Go Chiba; Kenichi Tada, Proc. M&C 2021, 710, 720, 03 Oct. 2021, [Peer-reviewed], [International Magazine]
A generation capability of neutron multi-group cross sections is being implemented to the FRENDY nuclear data processing code, as FRENDY/MG. FRENDY/MG generates neutron multi-group cross sections for deterministic core analysis codes considering an arbitrary energy group structure. Distinguished features of FRENDY/MG are 1) use of ACE pointwise cross sections as the source of nuclear data (no evaluated nuclear data file is directly used), 2) treatment of a compound material consisting of multiple nuclides to explicitly consider the resonance interference effect. Various verifications are being carried out through the comparison with the multi-group cross sections generated by NJOY., American Nuclear Society, English, Summary international conference

Multi-Group Cross Section Library Generation by FRENDY for Fast Reactor Neutronics Calculations
Go Chiba; Akio Yamamoto; Kenichi Tada; Tomohiro Endo, Transactions of the American Nuclear Society, 124, 556, 558, Jun. 2021, [Peer-reviewed], [International Magazine]
American Nuclear Society, English, Summary international conference

Verification of the Multi-Group Generation Capability of FRENDY Nuclear Data Processing Code for Recent Nuclear Data through Comparison of One-group Reaction Rates
Akio Yamamoto; Kenichi Tada; Go Chiba; Tomohiro Endo, Transactions of the American Nuclear Society, 124, 544, 547, Jun. 2021, [International Magazine]
American Nuclear Society, English, Summary international conference

Treatment of scattering sources in numerical calculations of the radiative transfer equation with discrete ordinates methods
清水亮輔; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2021, 2021

Improvement of high-efficiency random sampling method by using control variates method and sensitivity (2) Application to burnup characteristics of BWR fuel assembly
木田拓実; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2021, 2021

Study on Optimization of Fuel Composition for Reducing Sodium Void Reactivity in Sodium-Cooled Fast Reactor
大池宏弥; 遠藤知弘; 山本章夫; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2021, 2021

Development of pseudo FP generation algorithm for nuclear fuel burnup calculations (1) Outline of the algorithm
柳原健人; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2021, 2021

Development of pseudo FP generation algorithm for nuclear fuel burnup calculations (2) Numerical results
柳原健人; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2021, 2021

原子力エネルギーシステム応用の観点から
千葉豪, 核データニュース(Web), 123, 34‐41 (WEB ONLY), Jun. 2019
Japanese

核データ積分テスト計算への実効部分空間法の適用 2)
今里大智; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2019, ROMBUNNO.3J06, 04 Mar. 2019
Japanese

原子力エネルギーシステム応用の観点から
千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2019, ROMBUNNO.3E_PL04, 04 Mar. 2019
Japanese

21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(8)MAリサイクルを想定した高速炉の廃棄物特性評価
小林優; 千葉豪; 川久保政洋; 朝野英一, 日本原子力学会春の年会予稿集(CD-ROM), 2019, ROMBUNNO.1B08, 04 Mar. 2019
Japanese

21世紀後半に向けた廃棄物管理の選択肢:Pu利用推進と環境負荷低減型地層処分に関する研究(7)分離核種の燃焼を念頭に置いたCBZコードシステムを用いた高速炉燃焼計算
千葉豪; 川久保政洋; 朝野英一, 日本原子力学会春の年会予稿集(CD-ROM), 2019, ROMBUNNO.1B07, 04 Mar. 2019
Japanese

感度係数による不確かさ評価結果を類似対称に用いた,より効果的なMCCV法の提案
二平舜介; 千葉豪, 日本原子力学会秋の大会予稿集(CD-ROM), 2018, ROMBUNNO.1M03, 20 Aug. 2018
Japanese

CBZコードシステムを用いた,福島第一原子力発電所内部の放射能インベントリ解析の詳細化
石井亮憲; 千葉豪, 日本原子力学会秋の大会予稿集(CD-ROM), 2018, ROMBUNNO.3I10, 20 Aug. 2018
Japanese

加速器駆動システムによる核変換処理の実現に向けた基礎研究(6)U‐Pbゾーン炉心を用いたADS実験
PYEON Cheol Ho; 山中正朗; 渡辺賢一; 相澤直人; 遠藤知弘; 千葉豪; VAN ROOIJEN Wilfred G, 日本原子力学会秋の大会予稿集(CD-ROM), 2018, ROMBUNNO.2M02, 20 Aug. 2018
Japanese

加速器駆動システムによる核変換処理の実現に向けた基礎研究(7)動特性パラメータの実験解析
山中正朗; 遠藤知弘; 千葉豪; VAN ROOIJEN Wilfred G; PYEON Cheol Ho, 日本原子力学会秋の大会予稿集(CD-ROM), 2018, ROMBUNNO.2M03, 20 Aug. 2018
Japanese

炉物理コードシステムCBZへのガラーキン求積法の実装
千葉豪; 藤井宏之, 日本原子力学会秋の大会予稿集(CD-ROM), 2018, ROMBUNNO.2M20, 20 Aug. 2018
Japanese

On prediction accuracy of neutronics parameters of accelerator-driven system
Go Chiba; Tomohiro Endo; Wilfred Van Rooijen; Cheol Ho Pyeon, EPJ Web of Conferences, 146, 13 Sep. 2017, [Peer-reviewed]
English

多核種高除染性空気浄化システム開発による作業被曝低減化研究(8)フィルターエレメントに捕捉される放射能評価のための簡易ツールの開発
千葉豪; 石井亮憲; 小崎完; 奈良林直; 佐藤修彰, 日本原子力学会秋の大会予稿集(CD-ROM), 2017, ROMBUNNO.2F21, 29 Aug. 2017
Japanese

多核種高除染性空気浄化システム開発による作業被曝低減化研究(9)フィルターエレメントに捕捉される短半減期FPの放射能の評価
石井亮憲; 千葉豪; 小崎完; 奈良林直; 山本泰功, 日本原子力学会秋の大会予稿集(CD-ROM), 2017, ROMBUNNO.2F22, 29 Aug. 2017
Japanese

Implementation of Fuel Depletion Sensitivity Calculation Capability into a Deterministic Reactor Physics Code System CBZ for Accelerator-Driven Sub-System Multi-Cycle Burnup Calculations
G. Chiba; W. F; G. van Rooijen; T. Endo; C. H. Pyeon, Proc. Int. Conf. Mathematics & Computational Methods Applied to Nucl. Sci. & Eng. (M&C2017), Jeju, Korea, Apr. 16-20, (2017)., Apr. 2017, [Peer-reviewed]
English, Summary international conference

Nuclear Data-Induced Uncertainty Quantification of Neutron Multiplication Factor and Prompt Neutron Decay Constant for Pb-Bi loaded ADS Benchmark Problems at KUCA
T. Endo; G. Chiba; W. F; G. van Rooijen; M. Yamanaka; C. H. Pyeon, Proc. Int. Conf. Mathematics & Computational Methods Applied to Nucl. Sci. & Eng. (M&C2017), Jeju, Korea, Apr. 16-20, (2017)., Apr. 2017, [Peer-reviewed]
English, Summary international conference

Variance Reduction Factor Calculations for Neutronics Parameters of Accelerator-Driven System
G. Chiba; W. F; G. van Rooijen; T. Endo; C. H. Pyeon, Proc. Int. Conf. on the Physic of Reactors (PHYSOR2016), Sun Valley, Idaho, May 1-5, (2016)., May 2016, [Peer-reviewed]
English, Summary international conference

Analysis and Interpretation of the KUCA ADS Benchmarks with Deterministic Analysis Codes
W. F; G. van Rooijen; C. H. Pyeon; G. Chiba; T. Endo, Proc. Int. Conf. on the Physic of Reactors (PHYSOR2016), Sun Valley, Idaho, May 1-5, (2016)., May 2016, [Peer-reviewed]
English, Summary international conference

多核種高除染性空気浄化システム開発による作業被曝低減化研究(1)全体計画
奈良林直; 千葉豪; 小崎完; 増田隆夫; 中坂佑太; 佐藤修彰; 秋山大輔, 日本原子力学会春の年会予稿集(CD-ROM), 2016, ROMBUNNO.1D20, 16 Mar. 2016
Japanese

Nurturing Problem-Finding Skills in Graduate Students through Problem Based Learning Approaches
Ankit A. Ravankar; Shotaro Imai; Michiyo Shimamura; Go Chiba; Taichi Takasuka; Yasuhiro Yamanaka, PROCEEDINGS 2016 5TH IIAI INTERNATIONAL CONGRESS ON ADVANCED APPLIED INFORMATICS IIAI-AAI 2016, 542, 546, 2016, [Peer-reviewed]
English

Discussion on a method of Team-Based-Learning style lecture for graduate students in a research university
Shotaro Imai; Ankit A. Ravankar; Michiyo Shimamura; Taichi E. Takasuka; Go Chiba; Yasuhiro Yamanaka, PROCEEDINGS 2016 5TH IIAI INTERNATIONAL CONGRESS ON ADVANCED APPLIED INFORMATICS IIAI-AAI 2016, 537, 541, 2016, [Peer-reviewed]
English

B212 Improvement of Two-Phase Flow Stability for Filtered Containment Venting System Using Silver Zeolite
SHOBUKAWA Hideyuki; NARABAYASHI Tadashi; CHIBA Go; Sato Masanobu, National Symposium on Power and Energy Systems, 2015, 20, 221, 222, 07 Jun. 2015
We have conducted a series of experiments in order to investigate and improve the performance of the advanced filtered containment venting system: a visualization experiment to examine two-phase flow stability in a vertical tube, a superheated steam experiment with multi-layer orifices and a clogging experiment with metal filter and simulated grains. In the first experiment, several specific phenomena, such as chugging, CCFL and geysering, have been observed. Generation of superheated steam has been confirmed through the second experiment. Regarding the clogging experiment, whereas metal filter has not been clogged, accumulation of the simulated grains has been observed., The Japan Society of Mechanical Engineers, Japanese

B135 Evaluation on Decay Heat Removal Capability of Isolation Condenser for Depressurization iand Cooling System
NARABAYASHI Tadashi; SHIMOE Tomohiro; CHIBA Go; TSUJI Masashi; SAKASHITA Hiroto, National Symposium on Power and Energy Systems, 2014, 19, 73, 74, 25 Jun. 2014
In this study, we aimed to quantitatively evaluate cooling capacity of isolation condenser (IC) for core cooling in Fukushima Daiichi Nuclear Plant Unit 1. In order to evaluate cooling capacity, decay heat emitted from fuels in reactor core was calculated. We used the data of nuclear fuel and rated thermal power which is released by TEPCO. We analyzed IC with TRAC code. We made an experiment in order to check IC's input data. Because analysis data is close to experimental data, we made sure validity of input data. We analyzed IC under conditions which are recorded when IC started up and tsunami rushed toward plant. As a result of analysis, we confirmed that cooling capacity exceed decay heat under both conditions. In conclusion, IC had a capability to prevent core meltdown accident in Fukushima Daiichi Nuclear Plant Unit 1., The Japan Society of Mechanical Engineers, Japanese

B225 Molten Core Concrete Interaction and Development of Core Catcher
NARABAYASHI Tadashi; MIYAWAKI Daichi; SYLWESTER Marta Ziemnicka; CHIBA Go; TSUJI Masashi, National Symposium on Power and Energy Systems, 2014, 19, 257, 258, 25 Jun. 2014
Fukushima Daiichi NPP accident would be terminated, if sufficient accident countermeasures, such as water proof door, mobile power, etc. In case of Europe, it had already recommended to install core catcher from the lessons of Chernobyl Accidents. In this paper we introduce simplified core catch by using core catcher that used Basalt. Hokkaido University has tested the simplified core catcher, by using thermite process. We found that molten thermite debris and concrete interaction make concrete to erode on its surface. We also tested several ceramics such as SiC etc., to find suitable materials. But the ceramics was broken by thermal shock. Among these materials we recommend the Basalt for the material of the core catcher., The Japan Society of Mechanical Engineers, Japanese

トリウム装荷臨界実験に対する感度解析と不確かさ評価
田熊伸也; 千葉豪; 辻雅司; 奈良林直, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.O50, 10 Mar. 2014
Japanese

ランダムサンプリング法を用いた断面積調整法および感度係数評価(3)感度係数評価
千葉豪; 辻雅司; 奈良林直; 渡辺友章; 遠藤知弘; 山本章夫, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.O47, 10 Mar. 2014
Japanese

核種生成量に対する核データの感度解析
川本洋右; 千葉豪; 辻雅司; 奈良林直, 日本原子力学会春の年会予稿集(CD-ROM), 2014, ROMBUNNO.O49, 10 Mar. 2014
Japanese

Influences of Differences in Nuclear Data Libraries on Important Back-end Parameters
YOSHIDA SHOTA; CHIBA GO; TSUJI MASASHI; NARABAYASHI TADASHI, 日本原子力研究開発機構JAEA-Conf(Web), 2013-002, WEB ONLY 28, Oct. 2013
English

Validation of CBZ Code System for Post-Irradiation Examination Analysis and Sensitivity Analysis of (n,.GAMMA.) Branching Ratio
KAWAMOTO YOSUKE; CHIBA GO; TSUJI MASASHI; NARABAYASHI TADASHI, 日本原子力研究開発機構JAEA-Conf(Web), 2013-002, WEB ONLY 21, Oct. 2013
English

Validation of JENDL-4.0 and Future: Reactor Integral Test Working Group
CHIBA GO, 日本原子力研究開発機構JAEA-Conf(Web), 2013-002, WEB ONLY 12, Oct. 2013
English

高速炉蒸気発生器における伝熱管破損事象に関する研究(27)管群体系内の蒸気噴流可視化試験 第二報
加藤慶輔; 奈良林直; 辻雅司; 千葉豪; 大島宏之; 栗原成計; 内堀昭寛, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.J12, 20 Aug. 2013
Japanese

J‐PARC/MLF/ANNRI NaI(Tl)スペクトロメータ及びGeスペクトロメータを用いたGd‐157の中性子捕獲断面積の測定
木村敦; 廣瀬健太郎; 中村詔司; 原かおる; 原田秀郎; 千葉豪; 片渕竜也; 寺田和司; 水本元治; 井頭政之, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.C02, 20 Aug. 2013
Japanese

核特性パラメータの不確かさ評価における共鳴自己遮蔽効果
千葉豪; 辻雅司; 奈良林直, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.J21, 20 Aug. 2013
Japanese

特異値分解法による簡易燃焼チェーン自動作成ツールの開発
梶原孝則; 辻雅司; 千葉豪; 奈良林直; 大岡靖典; 牛尾直史, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.J28, 20 Aug. 2013
Japanese

原子力発電所の各種漏洩事象評価手法の高度化に関する研究(1)漏洩評価法の高度化研究の概要
岡田健志; 奈良林直; 辻雅司; 千葉豪; 尾形悠斗; 宮野廣; 松本昌昭, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.K49, 20 Aug. 2013
Japanese

ゼオライトを用いた高除染性フィルタードベントシステムの開発(5)フィルタードベントシステムの作動範囲とパラメータ試験
藤井康弘; 奈良林直; 佐藤修彰; 辻雅司; 千葉豪; 川本洋右, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.H50, 20 Aug. 2013
Japanese

非常用復水器を用いた過酷事故緩和に関する研究 高圧可視化実験装置を用いた実験
下江知弘; 奈良林直; 辻雅司; 千葉豪, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.H41, 20 Aug. 2013
Japanese

ゼオライトを用いた高除染性フィルタードベントシステムの開発(4)格納容器のFP保持機能を活かしたフィルタードベントシステム
奈良林直; 藤井康弘; 佐藤修彰; 辻雅司; 千葉豪, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.H49, 20 Aug. 2013
Japanese

原子力発電所の各種漏洩事象評価手法の高度化に関する研究(2)配管からの微小漏洩評価手法の開発
尾形悠斗; 奈良林直; 辻雅司; 千葉豪; 岡田健志; 松本昌昭; 宮野廣, 日本原子力学会秋の大会予稿集(CD-ROM), 2013, ROMBUNNO.K50, 20 Aug. 2013
Japanese

E113 Visualization Test of Filtered Vent and Evaluation of Source Term
FUJII Yasuhiro; KAWAMOTO Yosuke; NARABAYASHI Tadashi; TSUJI Masashi; CHIBA Go, National Symposium on Power and Energy Systems, 2013, 18, 151, 152, 19 Jun. 2013
This paper describes how to write a manuscript of the 18th PES Proceedings. In the Fukushima Daiichi Nuclear Power Plant accident, a great deal of radioactive material was released to surrounding environment After the accident, the Filtered Containment Venting System (FCVS) that can remove radioactive material from steam in containment vessel has attracted a great deal of attentions. However, there is few knowledge of filtered vent in Japan because almost filtered vent were developed in Europe after Chernobyl nuclear power plant accident. Therefore, our purpose is getting the knowledge of filtered vent through experiments that simulate various filter vents in Europe. Also using the knowledge gotten through experiment, we aim at developing high efficiency filtered containment venting system using zeolite., The Japan Society of Mechanical Engineers, Japanese

ND2013核データ国際会議報告(3)炉物理関連(積分実験)
福島昌弘; 千葉豪, 核データニュース(Web), 105, WEB ONLY 37-39, Jun. 2013
Japanese

高速炉蒸気発生器における伝熱管破損事象に関する研究(23)管群体系内の蒸気噴流可視化試験
加藤慶輔; 新栄邦彦; 奈良林直; 辻雅司; 千葉豪; 大島宏之; 栗原成計; 内堀昭寛, 日本原子力学会春の年会予稿集(CD-ROM), 2013, ROMBUNNO.N16, 11 Mar. 2013
Japanese

ゼオライトを用いた高除染性フィルタードベントシステムの開発(1)フィルタードベントシステムの基本構成の検討と放射性核種吸着実験
奈良林直; 藤井康弘; 佐藤修彰; 辻雅司; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2013, ROMBUNNO.M08, 11 Mar. 2013
Japanese

一般化摂動論を用いた燃焼感度の計算
千葉豪; 辻雅司; 奈良林直, 日本原子力学会春の年会予稿集(CD-ROM), 2013, ROMBUNNO.H46, 11 Mar. 2013
Japanese

ゼオライトを用いた高除染性フィルタードベントシステムの開発(2)フィルター内流動可視化試験
藤井康弘; 奈良林直; 佐藤修彰; 辻雅司; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2013, ROMBUNNO.M09, 11 Mar. 2013
Japanese

ゼオライトを用いた高除染性フィルタードベントシステムの開発(3)多核種解析法によるソースタームと崩壊熱計算
川本洋右; 藤井康弘; 奈良林直; 佐藤修彰; 辻雅司; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2013, ROMBUNNO.M10, 11 Mar. 2013
Japanese

動特性同定法によるもんじゅの反応度温度係数の測定
佐久間渉; 辻雅司; 奈良林直; 千葉豪, KURRI KR (CD) (CD-ROM), 39, ROMBUNNO.8, 2013
Japanese

過酷事故緩和に対する深層防護の強化の提案(3)可視化試験結果
藤井康弘; 奈良林直; 石田和輝; 千葉豪, 日本原子力学会秋の大会予稿集(CD-ROM), 2012, ROMBUNNO.M39, 346, 03 Sep. 2012
蒸気を用いたフィルター付ベントシステムの可視化試験試験を実施して、フィルター部の流動特性や圧力損失の測定、ミストセパレータの液滴除去特性について測定した。また、ゼオライトのセシウム吸着特性についても測定し、ゼオライトを用いたフィルタードベントシステムの放射性物質の除去特性についても基礎実験を行った。, Atomic Energy Society of Japan, Japanese

一点炉随伴動特性方程式を用いた原子炉ペリオドの感度解析
千葉豪; 辻雅司; 奈良林直, 日本原子力学会秋の大会予稿集(CD-ROM), 2012, ROMBUNNO.Q49, 173, 03 Sep. 2012
遅発中性子先行核を陽に扱った一点炉随伴動特性方程式を用いて、原子炉ペリオドの核データに対する感度解析を行った。, Atomic Energy Society of Japan, Japanese

詳細燃焼チェーンを用いた高速炉全炉心計算
吉田将太; 千葉豪; 奈良林直; 辻雅司, 日本原子力学会秋の大会予稿集(CD-ROM), 2012, ROMBUNNO.Q17, 141, 03 Sep. 2012
バックエンド諸量の正確な評価のために核分裂生成物核種200程度を陽に扱った高速炉全炉心計算を行った。また、簡略化したモデルによる計算結果の誤差を定量的に評価した。, Atomic Energy Society of Japan, Japanese

Analysis of Radioactivity of the Ground Surface Measured at the Fukushima-Daiichi Nuclear Power Plant Site
CHIBA GO, 日本原子力研究開発機構JAEA-Conf(Web), 2012-001, WEB ONLY 23, Jul. 2012
English

Development of a Standard Data Base for FBR Core Design (XIV)-Analyses of Extensive FBR Core Characteristics Based on JENDL-4.0-
SUGINO KAZUTERU; ISHIKAWA MAKOTO; NUMATA KAZUYUKI; NUMATA KAZUYUKI; IWAI TAKEHIKO; IWAI TAKEHIKO; JIN TOMOYUKI; JIN TOMOYUKI; NAGAYA YASUNOBU; HAZAMA TAIRA; CHIBA GO; CHIBA GO; YOKOYAMA KENJI; KUGO TERUHIKO, 日本原子力研究開発機構JAEA-Research(Web), 2012-013, WEB ONLY, Jul. 2012
Japanese

海外の過酷事故対策の取り組みとフィルター付ベント
奈良林直; 杉山憲一郎; 石田和輝; 辻雅司; 千葉豪; 岡本孝司; 水町渉, 日本機械学会動力・エネルギー技術シンポジウム講演論文集, 17th, 17, 335, 338, 20 Jun. 2012
Fukushima Daiichi NPP accident would be terminated, if sufficient examination leads to install countermeasures, such as water proof door, mobile power, etc. In case of US, Diablo Canyon NPP in Florida, they have a water proof hatch type door and snorkel piping for the seawater pump motor. In case of Europe, it had already installed the heat removal system and filtered containment venting system from the lessons of TMI and Chernobyl Accidents. Decay heat removal system and CV spray cooling system with FCVS are ensured by using mobile generators and heat exchangers to keep the ultimate heat sink even in any natural disaster, such as large earthquake, big tsunami, sudden flooding etc. In this paper we introduce such technology and fundamental test for the filtered venting system, conducted by Hokkaido University., The Japan Society of Mechanical Engineers, Japanese

福島第1原子力発電所の非常用復水器の除熱能力評価
下江知弘; 奈良林直; 辻雅司; 千葉豪, 日本機械学会動力・エネルギー技術シンポジウム講演論文集, 17th, 17, 333, 334, 20 Jun. 2012
In this study, we aimed to quantitatively evaluate cooling capacity of isolation condenser (IC) for core cooling in Fukushima Daiichi Nuclear Plant Unit 1. In order to evaluate cooling capacity, we calculated decay heat which was emitted from core. We used the data of nuclear fuel and rated thermal power which is released by TEPCO. Analysis was conducted with TRAC code. We made an experiment in order to check input data for IC. Because analysis data was close to experimental data, we made sure of validity of input data. We analyzed IC under conditions which were recorded when IC started up and tsunami rushed toward plant. As a result of analysis, we confirmed that cooling capacity exceed decay heat under both conditions. In conclusion, IC had a capacity to prevent core meltdown accident in Fukushima Daiichi Nuclear Plant Unit 1., The Japan Society of Mechanical Engineers, Japanese

惑星間航行用原子力推進宇宙船の放射線遮蔽と居住性評価
岡田健志; 奈良林直; 辻雅司; 千葉豪, 日本機械学会動力・エネルギー技術シンポジウム講演論文集, 17th, 17, 327, 328, 20 Jun. 2012
The space development is our big dream. One of this is foray into deep space. And so we must have too large amount of power because missions in space is highly-developed and protracted, and in addition, devices are complicated and big with the space development. Nuclear power generation is good choice to these problems since it has such good points as big electric-generating capacity in the proximity of scale and weight of the facility. There our laboratory has researched about a nuclear spaceship. Especially this paper deals with living space in a nuclear spaceship. For example space has big difference in temperature and nuclear reactor releases radiation. The crew is needed to protect from such danger. First we did reproductive experiment of big difference in temperature in space as a basic experiment of heat insulation and researched the possibility of insulation by insulating material of urethane foam. Next we tried a design of shielding system by using a calculation code., The Japan Society of Mechanical Engineers, Japanese

過酷事故緩和に対する深層防護の強化の提案(2)フィルター付ベントシステムの基礎試験
奈良林直; 杉山憲一郎; 石田和輝; 水谷一貴; 千葉豪, 日本原子力学会春の年会予稿集(CD-ROM), 2012, ROMBUNNO.G40, 02 Mar. 2012
Japanese

多様な原子力システム間のバックエンド諸量の定量的比較
吉田将太; 千葉豪; 奈良林直; 辻雅司, 日本原子力学会北海道支部研究発表会講演要旨集, 30th, 19, 20, 2012
Japanese

動特性同定法を用いた高速増殖炉もんじゅの反応度温度係数の測定
佐久間渉; 辻雅司; 奈良林直; 千葉豪, 日本原子力学会北海道支部研究発表会講演要旨集, 30th, 21, 22, 2012
Japanese

Uncertainty Quantification of Doppler Coefficient for MONJU
CHIBA GO; CHIBA GO; HAZAMA TAIRA; KINJO HIDEHITO; KINJO HIDEHITO; NISHI HIROSHI; SUZUKI TAKAYUKI, 日本原子力研究開発機構JAEA-Research(Web), 2011, 2011-034, WEB ONLY, 2,1-42, Dec. 2011
日本原子力研究開発機構, Japanese

Uncertainty Quantification of Doppler Coefficient for MONJU
千葉 豪; 羽様 平; 金城 秀人, JAEA-research, 2011, 34, 巻頭1, 2,1-42, Dec. 2011
日本原子力研究開発機構, Japanese

Sensitivity Analysis for Higher Order Legendre Coefficients of Elastic Scattering Matrices
CHIBA Go, 日本原子力研究開発機構JAEA-Conf(Web), 2011-002, WEB ONLY 38, Sep. 2011
English

Sensitivity Analysis for Curium Isotope Concentrations of Light Water Reactor Mixed-Oxide Burned Fuel
CHIBA Go; ISHIKAWA Makoto, 日本原子力研究開発機構JAEA-Conf(Web), 2011-002, WEB ONLY 37, Sep. 2011
English

Improved Derivation of Multigroup Effective Cross Section for Heterogeneous System by Equivalence Theory
A. Yamamoto; T. Endo; G. Chiba, Nucl. Sci. Eng, 168, 75-92, 92, Jun. 2011, [Peer-reviewed]
English, Report scientific journal

On the cell homogenization for a lattice composed of asymmetric unit cells
CHIBA Go,VAN; ROOIJEN W.F.G, 日本原子力学会春の年会予稿集(CD-ROM), 2011, ROMBUNNO.F21, 11 Mar. 2011
English

Diffusion coefficients for asymmetric unit cells
VAN ROOIJEN; W.F.G; CHIBA Go, 日本原子力学会春の年会予稿集(CD-ROM), 2011, ROMBUNNO.F20, 11 Mar. 2011
English

Study on Calculation Methods for the Effective Delayed Neutron Fraction
IRWANTO Dwi; IRWANTO Dwi; CHIBA Go; NAGAYA Yasunobu; OBARA Toru; OBARA Toru, 日本原子力研究開発機構JAEA-Research(Web), 2010, 2010-061, WEB ONLY, 28,巻頭1-2, Mar. 2011
日本原子力研究開発機構, English

Development of the Next Generation Reactor Analysis Code System, MARBLE
YOKOYAMA KENJI; TATSUMI MASAHIRO; TATSUMI MASAHIRO; HIRAI YASUSHI; HIRAI YASUSHI; HYODO HIDEAKI; HYODO HIDEAKI; NUMATA KAZUYUKI; NUMATA KAZUYUKI; IWAI TAKEHIKO; IWAI TAKEHIKO; JIN TOMOYUKI; JIN TOMOYUKI; HAZAMA TAIRA; NAGAYA YASUNOBU; CHIBA GO; KUGO TERUHIKO; ISHIKAWA MAKOTO, 日本原子力研究開発機構JAEA-Data/Code(Web), 2010-030, WEB ONLY, Mar. 2011
Japanese

Study on Calculation Methods for the Effective Delayed Neutron Fraction
IRWANTO Dwi; 千葉 豪; 長家 康展, JAEA-research, 2010, 61, 1, 28,巻頭1-2, Mar. 2011
日本原子力研究開発機構, English

金属ウラン・ジルコニウムマトリックス燃料を装荷した小型PWRに関する研究
高田祐太; 奈良林直; 辻雅司; 千葉豪; 島津洋一郎, 日本原子力学会北海道支部研究発表会講演要旨集, 29th, 17, 18, 2011
Japanese

福島第一原子力発電所構内土壌の放射能データの解析
千葉豪; 杉山憲一郎; 片倉純一, 日本原子力学会北海道支部研究発表会講演要旨集, 29th, 31, 32, 2011
Japanese

Evaluation of Gamma-Ray Transport Effect on Heating Distribution in a Fast Reactor Fuel Subassembly
CHIBA GO, 日本原子力研究開発機構JAEA-Research(Web), 2010-045, WEB ONLY, Jan. 2011
Japanese

Analysis of MOZART Critical Experiment Using the IRPhEP Handbook Data
千葉 豪, JAEA-research, 2010, 42, 1, 92,巻頭1-2, Jan. 2011
日本原子力研究開発機構, Japanese

Evaluation of Gamma-Ray Transport Effect on Heating Distribution in a Fast Reactor Fuel Subassembly
千葉 豪, JAEA-research, 2010, 45, 1, 24,巻頭1-2, Jan. 2011
日本原子力研究開発機構, Japanese

Uncertainty Quantification of Lumped Fission Product Cross Section for Fast Reactor Application
CHIBA Go, 日本原子力研究開発機構JAEA-Conf(Web), 2010-005, WEB ONLY 9, Dec. 2010
English

Plan of the JENDL-4 Benchmark for Fast Reactors
SUGINO Kazuteru; CHIBA Go, 日本原子力研究開発機構JAEA-Conf(Web), 2010-005, WEB ONLY 7, Dec. 2010
English

Analysis of MOZART Critical Experiment Using the IRPhEP Handbook Data
CHIBA GO, 日本原子力研究開発機構JAEA-Research(Web), 2010-042, WEB ONLY, Dec. 2010
Japanese

原子力開発のための中性子核反応データベース 評価済み核データライブラリーJENDL‐4.0の完成
柴田恵一; 岩本修; 千葉豪, ΑΤΟΜΟΣ, 52, 12, 801, 805, 01 Dec. 2010
日本原子力学会, Japanese

JENDL-4.0 : A Database on Neutron-induced Reactions for Nuclear Science and Engineering
SHIBATA Keiichi; IWAMOTO Osamu; CHIBA Go, Ατομοσ, 52, 12, 801, 805, 01 Dec. 2010
日本原子力学会, Japanese

Development of Gamma Cross Section Library for Fast Reactor Gamma Heating Calculations
CHIBA GO; HAZAMA TAIRA; SUZUKI TAKAYUKI, 日本原子力研究開発機構JAEA-Data/Code(Web), 2010-013, WEB ONLY, Sep. 2010
Japanese

Calculation of diffusion coefficients for voided lattices with the method of characteristics: II: numerical results
CHIBA Go,VAN; ROOIJEN W.F.G, 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.Q36, 27 Aug. 2010
English

Calculation of diffusion coefficients for voided lattices with the method of characteristics: I: theory
VAN ROOIJEN; W.F.G; CHIBA Go, 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.Q35, 27 Aug. 2010
English

二項有理式近似を用いたToneの手法の改良
山本章夫; 遠藤知弘; 千葉豪, 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.Q42, 27 Aug. 2010
Japanese

べき乗法の収束残差からの高次固有値の推定
中瀬正彦; 千葉豪; 齊藤正樹, 日本原子力学会春の年会予稿集(CD-ROM), 2010, ROMBUNNO.G19, 09 Mar. 2010
Japanese

高速炉用オブジェクト統合型解析システムの研究開発―(11)次世代炉物理解析システムMARBLE1.0の完成―
横山賢治; 巽雅洋; 平井康志; 兵頭秀昭; 沼田一幸; 岩井武彦; 神智之; 羽様平; 長家康展; 千葉豪; 久語輝彦; 石川眞, 日本原子力学会春の年会予稿集(CD-ROM), 2010, ROMBUNNO.G30, 09 Mar. 2010
Japanese

「JENDL‐4の完成と今後の展望」核分裂炉に対するJENDL‐4.0の積分テスト
千葉豪; 奥村啓介; 杉野和輝, 日本原子力学会春の年会予稿集(CD-ROM), 2010, ROMBUNNO.JS03, 09 Mar. 2010
Japanese

Incorporation of Two-Term Rational Approximation in Tone Method for Resonance Calculation
YAMAMOTO Akio; ENDO Tomohiro; CHIBA Go, Trans Am Nucl Soc, 103, 711, 713, 2010
English

Towards the Completion of JENDL-4: Current Status of Integral Test
CHIBA Go; OKUMURA Keisuke, 日本原子力研究開発機構JAEA-Conf, 21, 26, Oct. 2009
English

Benchmarking of Effective Delayed Neutron Fraction With Deterministic Method
IRWANTO Dwi; OBARA Toru; CHIBA Go, 日本原子力研究開発機構JAEA-Conf, 151, 156, Oct. 2009
English

Nuclear Data-Induced Uncertainty Calculation for Fast Reactor Eigenvalue Separation
CHIBA Go, 日本原子力研究開発機構JAEA-Conf, 101, 106, Oct. 2009
English

Criticality Calculations with Fission Spectrum Matrix
CHIBA Go, 日本原子力研究開発機構JAEA-Conf, 107, 110, Oct. 2009
English

軽水炉使用済燃料核種インベントリに対する燃焼感度解析
千葉豪; 奥村啓介, 日本原子力学会秋の大会予稿集(CD-ROM), 2009, F26, 28 Aug. 2009
Japanese

Calculations of Kobayashi Benchmark Problems with a Neutron Transport Simulation Code System CBG
CHIBA GO, 日本原子力研究開発機構JAEA-Research, 2009, 12, 51P, 43,巻頭1〜2, Jul. 2009
日本原子力研究開発機構, Japanese

Calculations of Kobayashi benchmark problems with a neutron transport simulation code system CBG
千葉 豪, JAEA-research, 2009, 12, 1, 43,巻頭1〜2, Jul. 2009
日本原子力研究開発機構, Japanese

Study on Calculation Methods for Effective Delayed Neutron Fraction
IRWANTO Dwi; OBARA Toru; CHIBA Go; NAGAYA Yasunobu, 日本原子力学会春の年会予稿集(CD-ROM), 2009, K30, 06 Mar. 2009
English

原子炉計算用多群ライブラリの精度向上方策の検討(2)
千葉豪; 奥村啓介, 日本原子力学会春の年会予稿集(CD-ROM), 2009, K45, 06 Mar. 2009
Japanese

Convariances of Resonance Self-Shielding Factor and its Temperature Gradient for Uncertainty Evaluation of Doppler Reactivity
ZUKERAN Atsushi; CHIBA Go; OTUKA Naohiko; ISHIKAWA Makoto; TAKANO Hideki, 日本原子力研究開発機構JAEA-Research, 2008, 91, 174P, 162,巻頭1〜2, Feb. 2009
日本原子力研究開発機構, English

Covariances of resonance self-shielding factor and its temperature gradient for uncertainty evaluation of Doppler reactivity
瑞慶覧 篤; 千葉 豪; 大塚 直彦, JAEA-research, 2008, 91, 1, 162,巻頭1〜2, Feb. 2009
日本原子力研究開発機構, English

Covariance Evaluation of Self-Shielding Factor and Its Temperature Gradient for Uncertainty Evaluation of Doppler Reactivity
OTSUKA Naohiko; OTSUKA Naohiko; ZUKERAN Atsushi; TAKANO Hideki; CHIBA Go; ISHIKAWA Makoto, 日本原子力研究開発機構JAEA-Conf, 32, 40, Nov. 2008
English

CBGLIB: A Multi-group Neutron Library for Precise Neutronics Simulations
CHIBA Go, 日本原子力研究開発機構JAEA-Conf, 114, 120, Nov. 2008
English

Nuclear Data Benchmark for Sodium Voided Reactivity Worth with Improved Neutronics Simulation Method
CHIBA Go, 日本原子力研究開発機構JAEA-Conf, 108, 113, Nov. 2008
English

Benchmark Test of Evaluated Nuclear Data Files for Development of JENDL-4
CHIBA GO; OKUMURA KEISUKE, 日本原子力研究開発機構JAEA-Research, 2008, 89, 58P, 48,巻頭1〜9, Nov. 2008
日本原子力研究開発機構, Japanese

Benchmark test of evaluated nuclear data files for development of JENDL-4
千葉 豪; 奥村 啓介, JAEA-research, 2008, 89, 1, 48,巻頭1〜9, Nov. 2008
日本原子力研究開発機構, Japanese

Nuclear Data Needs for Fast Reactors
CHIBA Go, 日本原子力研究開発機構JAEA-Conf, 26, 31, Sep. 2008
English

核分裂スペクトルに関する実効増倍率の不確定性についての考察
長家康展; 千葉豪; 石川眞, 日本原子力学会秋の大会予稿集(CD-ROM), 2008, A23, 21 Aug. 2008
Japanese

ERRORF-A Code to Calculate Covariance of Self-shielding Factor and Its Temperature Gradient
OTUKA Naohiko; ZUKERAN Atsushi; TAKANO Hideki; CHIBA Go; ISHIKAWA Makoto, 日本原子力研究開発機構JAEA-Data/Code, 21P, Jun. 2008
English

モジュラー型炉心解析コードシステムMOSRAの開発
奥村啓介; 久語輝彦; 中野佳洋; 長家康展; 小嶋健介; 千葉豪; 岡嶋成晃, 日本原子力学会春の年会予稿集(CD-ROM), 2008, L46, 11 Mar. 2008
Japanese

原子炉計算用多群ライブラリの精度向上方策の検討
千葉豪; 奥村啓介, 日本原子力学会春の年会予稿集(CD-ROM), 2008, L30, 11 Mar. 2008
Japanese

積分データによる理論計算パラメータ及び微分核データの調整
千葉敏; 岩本修; 中川庸夫; 千葉豪; 奥村啓介, 日本原子力学会春の年会予稿集(CD-ROM), 2008, B20, 11 Mar. 2008
Japanese

中性子輸送ベンチマーク問題のための参照解の計算
千葉豪; 沼田一幸, 日本原子力研究開発機構JAEA-Review, 119, Feb. 2008
Japanese

マイナーアクチニド核データの積分テスト
千葉豪; 奥村啓介, 日本原子力学会秋の大会予稿集(CD-ROM), 2007, M12, 07 Sep. 2007
Japanese

Benchmark Test of Evaluated Nuclear Data Files for Fast Reactor Neutronics Application
CHIBA GO; IWAI TAKEHIKO; NUMATA KAZUYUKI; HAZAMA TAIRA, 日本原子力研究開発機構JAEA-Research, 62P, Jul. 2007
Japanese

ロスアラモス体験記-核データ部会「若手研究者LANL夏期国際交流プログラム」報告
千葉 豪, 日本原子力学会誌 = Journal of the Atomic Energy Society of Japan, 49, 3, 211, 212, 28 Mar. 2007
Japanese

分離及び非分離共鳴領域における共分散行列の評価と処理(SG‐20)
千葉豪, 日本原子力学会春の年会要旨集(CD-ROM), 2007, TD02, 06 Mar. 2007
Japanese

高速炉用オブジェクト統合型解析システムの研究開発―(7)中性子輸送ソルバーの開発と検証―
千葉豪, 日本原子力学会春の年会要旨集(CD-ROM), 2007, J35, 06 Mar. 2007
Japanese

反射体の材質変更による「常陽」運転用燃料の利用効率改善
関根隆; 大川内靖; 千葉豪; 伊東秀明; 青山卓史, 日本原子力学会春の年会要旨集(CD-ROM), 2007, H38, 06 Mar. 2007
Japanese

ERRORJ: A Code to Process Neutron-nuclide Reaction Cross Section Covariance, Version 2.3
CHIBA Go, 日本原子力研究開発機構JAEA-Data/Code, 26P, Mar. 2007
English

鉄に感度を有する高速炉炉心の臨界性解析
千葉豪, 日本原子力学会和文論文誌, 4, 1, 66, 76, 25 Mar. 2005
日本原子力学会, Japanese

高速実験炉「常陽」MK‐III性能試験‐制御棒校正(NT‐321)‐
千葉豪; 北野彰洋; 前田茂貴; 関根隆, 核燃料サイクル開発機構公開資料, 90P, Oct. 2004
Japanese

工学系モデリング言語としての次世代解析システムの開発(IV)‐境界要素法に基づく中性子拡散ソルバーの開発‐
千葉豪, 核燃料サイクル開発機構公開資料, 54P, Oct. 2004
Japanese

工学系モデリング言語としての次世代解析システムの開発(III)‐プロトタイプ作成による検討(その2)‐
横山賢治; 細貝広視; 千葉豪; 笠原直人; 石川真, 核燃料サイクル開発機構公開資料, 164P, Apr. 2004
Japanese

「常陽」MK‐III性能試験―(4)制御棒反応度価値―
千葉豪; 加藤優子; 服部和裕; 関根隆, 日本原子力学会春の年会要旨集, 42nd, 525, 11 Mar. 2004
Japanese

SLAROM‐UF:高速炉用超微細群格子計算コード(マニュアル)
羽様平; 千葉豪; 佐藤若英; 沼田一幸, 核燃料サイクル開発機構公開資料, 94P, Mar. 2004
Japanese

"JOYO" MK-III Core Performance Tests and Results
MAEDA SHIGETAKA; YOKOYAMA KENJI; CHIBA GO; SEKINE TAKASHI; AOYAMA TAKAFUMI, サイクル機構技報, 21, 99, 109, 20 Dec. 2003
Japanese

MK-3性能試験計画と試験結果 (特集 高速実験炉「常陽」の高度化計画(MK-3計画)と今後の展望) -- (総合機能試験と性能試験)
前田 茂貴; 横山 賢治; 千葉 豪, サイクル機構技報, 0, 21, 99, 109, Dec. 2003
核燃料サイクル開発機構技術展開部, Japanese

サブグループパラメータ計算コードMOMENTOFの開発
千葉豪, 核燃料サイクル開発機構公開資料, 27P, Jul. 2003
Japanese

高速炉体系におけるJENDL‐3.3の積分テスト
千葉豪; 羽様平; 佐藤若英; 沼田一幸, 核燃料サイクル開発機構公開資料, 48P, May 2003
Japanese

高速炉核特性に対するJENDL‐3.3の積分テスト
羽様平; 千葉豪, 日本原子力学会春の年会要旨集, 41st, 405, 05 Mar. 2003
Japanese

高速炉における格子計算手法の比較
千葉豪, 日本原子力学会春の年会要旨集, 41st, 395, 05 Mar. 2003
Japanese

Computer Code System for the R&D of Nuclear Fuel Cycle with Fast Reactor. V. Development and Application of Reactor Analysis Code System.
YOKOYAMA KENJI; HAZAMA TAIRA; CHIBA GO; OKI SHIGEO; ISHIKAWA MAKOTO, サイクル機構技報, 17, 19, 30, 20 Dec. 2002
核燃料サイクル開発機構技術展開部, Japanese

高速炉核特性解析における炉定数高度化の効果に関する検討
千葉豪, 核燃料サイクル開発機構公開資料, 30P, Dec. 2002
Japanese

技術報告 高速炉サイクルの研究開発を支える解析システム(5)核特性解析コードシステムの開発と利用
横山 賢治; 羽様 平; 千葉 豪, サイクル機構技報, 0, 17, 19, 30, Dec. 2002
核燃料サイクル開発機構技術展開部, Japanese

統合炉定数ADJ2000の使用に係る炉定数効果の評価(研究報告書)
庄野彰; 千葉豪; 沼田一幸, 核燃料サイクル開発機構公開資料, 38P, Nov. 2002
Japanese

高速炉用統合炉定数ADJ2000Rの作成 (研究報告)
羽様平; 千葉豪; 沼田一幸; 佐藤若英, 核燃料サイクル開発機構公開資料, 333P, Nov. 2002
Japanese

高速炉格子計算手法の比較研究
千葉豪, 核燃料サイクル開発機構公開資料, 87P, Oct. 2002
Japanese

次世代炉定数システムによる高速炉核特性解析 (II) 次世代炉定数システム導入による効果
千葉豪; 杉野和輝; 石川真; 沼田一幸, 日本原子力学会春の年会要旨集, 40th, 285, 05 Mar. 2002
Japanese

次世代炉定数システムによる高速炉核特性解析 (I) JFS‐3‐J3.2作成時の重み関数訂正効果
千葉豪; 杉野和輝; 石川真; 沼田一幸, 日本原子力学会春の年会要旨集, 40th, 284, 05 Mar. 2002
Japanese

JENDL‐3.2に基づく高速炉用炉定数JFS‐3‐J3.2Rの作成
千葉豪; 沼田一幸, 核燃料サイクル開発機構公開資料, 45P, Feb. 2002
Japanese

The revision of nuclear constant set for fast reactor, JFS-3-J3.2
Gou Chiba; Taira Hazama; Makoto Ishikawa, Transactions of the Atomic Energy Society of Japan, 1, 4, 335, 340, 2002
日本原子力学会, English

Evaluation of an Effect on Nuclear Characteristics by Correcting the Weighting Function in JFS-3-J3.2.
CHIBA GO; NUMATA KAZUYUKI, JFS-3-J3.2の重み関数訂正による核特性への影響評価 (研究報告) 平成13年, 60P, 2001
Japanese

階層領域分割型境界要素法による中性子拡散方程式解法の並列化 (II) 通信の並列化による高速化
辻雅司; 千葉豪, 日本原子力学会春の年会要旨集, 37th, 386, 22 Mar. 1999
Japanese

原子炉の物理
11章（発熱と伝熱、発電）
日本原子力学会, Dec. 2019, [Contributor]

エネルギー環境システム工学特別ラボラトリーセミナー, 2024年, 修士課程, 工学院

原子炉工学特論, 2024年, 修士課程, 工学院

原子炉物理特論, 2024年, 修士課程, 工学院

原子炉特別実験, 2024年, 修士課程, 工学院

原子力・エネルギーシステム特論, 2024年, 修士課程, 工学院

エネルギー環境システム工学特別ラボラトリーセミナー, 2024年, 博士後期課程, 工学院

原子炉工学特論, 2024年, 博士後期課程, 工学院

原子炉物理特論, 2024年, 博士後期課程, 工学院

原子炉特別実験, 2024年, 博士後期課程, 工学院

原子力・エネルギーシステム特論, 2024年, 博士後期課程, 工学院

一般教育演習(ﾌﾚｯｼｭﾏﾝｾﾐﾅｰ), 2024年, 学士課程, 全学教育

エネルギー工学概論, 2024年, 学士課程, 工学部

環境エネルギー工学, 2024年, 学士課程, 工学部

原子炉工学, 2024年, 学士課程, 工学部

原子炉物理, 2024年, 学士課程, 工学部

科学・技術の世界, 2024年, 学士課程, 全学教育

Development of fast and accurate advanced burnup and activation calculation method for nuclear safety
Grants-in-Aid for Scientific Research
01 Apr. 2024 - 31 Mar. 2027
山本 章夫; 渡邉 友章; 千葉 豪; 相澤 直人
Japan Society for the Promotion of Science, Grant-in-Aid for Scientific Research (C), Nagoya University, 24K08300

原子力発電プラント構造物の放射化計算のための革新的超高速計算フレームワーク
科学研究費助成事業
01 Apr. 2022 - 31 Mar. 2025
千葉 豪
日本学術振興会, 基盤研究(C), 北海道大学, 22K04979

TM-EFP: an inovative numerical model for nuclear reactor transient analyses
Grants-in-Aid for Scientific Research
01 Apr. 2016 - 31 Mar. 2019
Chiba Go
Delayed neutrons play an important role in nuclear energy utilization by human being, and delayed neutron emission is important physical phenomena which should be considered especially in safety analyses of nuclear reactors. The conventional model which has been widely and generally used in the world introduces an approximation that various fission product nuclides are treated as small number of fictitious nuclides, but we propose and develop a more sophisticated model which can handle with all the fission product nuclides explicitly and realize spatially-dependent nuclear reactor kinetics calculations with this model. As an example, nuclear reactor transient problems with leakage of gaseous fission product nuclides are carried out, and effectiveness of this model is demonstrated.
Japan Society for the Promotion of Science, Grant-in-Aid for Young Scientists (B), Hokkaido University, 16K18344

Uncertainty quantification of reactor analysis method at design extension condition: A new estimation method based on covariance between input and prediction error
Grants-in-Aid for Scientific Research
01 Apr. 2016 - 31 Mar. 2019
Yamamoto Akio; Khalik Abdel Hany
A new evaluation method for prediction error of neutronics simulations under severe accident conditions of a nuclear reactor has been developed. The present method utilizes the Kriging method, which is used in the field of geostatstics, and the principal component analysis. Calculation error of simulation is evaluated by learning the correlation between the parameters used in the simulation and the calculation errors.
The present method is applied to predict the error of effective multiplication factor of LWR fuel assemblies for various conditions including from normal operation to severe accident conditions. The difference of multiplication factors obtained by the deterministic and the continuous energy Monte-Carlo methods is considered as the calculation error. The results indicate that the present method accurately estimates the calculation error for wide range of reactor conditions.
Japan Society for the Promotion of Science, Grant-in-Aid for Scientific Research (C), Nagoya University, 16K06956

Uncertainty estimation of unmeasurable core safety parameters - a new approach using covariance matrix
Grants-in-Aid for Scientific Research
01 Apr. 2012 - 31 Mar. 2015
YAMAMOTO Akio; CHIBA Go; ENDO Tomohiro
In the present study, uncertainty estimation of unmeasurable core neutronics parameters is studied, especially theoretical framework and implementation of numerical methods, and validity of the developed methods is confirmed through verifications. A new approach for the cross section adjustment and the bias factor method is developed based on the random sampling method in order to apply them to actual light water reactors. All goals of the present study are fulfilled and the above achievements are beyond the plan at the beginning of this study.
Japan Society for the Promotion of Science, Grant-in-Aid for Scientific Research (C), Nagoya University, 24561040

Development of High Efficiency Filtered Containment Venting System by using AgX
Grants-in-Aid for Scientific Research
01 Apr. 2012 - 31 Mar. 2015
NARABAYASHI Tadashi; SATO Masanobu; TSUJI Masashi; CHIBA Go
From the lessons of TMI and Chernobyl Accidents, filtered containment venting system (FCVS) and Containment vessel spray cooling system are enforced in the the New Regulatory Requirement, by using mobile generators and heat exchangers to keep the ultimate heat sink even in any natural disaster, such as large earthquake, big tsunami etc. In this study we have succeeded to develop high decontamination factor FCVS that used Silver Zeolite named AgX. Hokkaido University has tested wet type FCVS using venturi scrubber in hot water pool and dry type FCVS using metallic fiber filter for 1st stage and AgX for 2nd stage, generating super heat steam by using multi-stage orifice. Tohoku University succeeded to use silver doped zeolite (AgX) which is a promising sorbent for CH3I can remove over 99.99%. The results are the 1st class high decontamination factor and applied to actual Nuclear power plants in Japan.
Japan Society for the Promotion of Science, Grant-in-Aid for Scientific Research (B), Hokkaido University, 24360388