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Nuclear Technology Volume 137, 2002 - Issue 2
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Technical Paper

Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels

Yoshinori NakaharaJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
,
Kenya SuyamaJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
,
Jun InagawaJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
,
Ryuji NagaishiJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
,
Setsumi KurosawaJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
,
Nobuaki KohnoJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
,
Mamoru OnukiJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
&
Hiroki MochizukiJapan Atomic Energy Research Institute, Tokai-mura, Naka-gun, 319-1195, Japan
 show all
Pages 111-126 | Published online: 13 May 2017

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Tomoaki Watanabe, Kenichi Tada, Tomohiro Endo & Akio Yamamoto. (2023) Impact of nuclear data revised from JENDL-4.0 to JENDL-5 on PWR spent fuel nuclide composition. Journal of Nuclear Science and Technology 60:11, pages 1386-1396.
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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. (2023) Japanese evaluated nuclear data library version 5: JENDL-5. Journal of Nuclear Science and Technology 60:1, pages 1-60.
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A. Nava-Dominguez, S. Liu, T. Beuthe, B. P. Bromley & A. V. Colton. (2021) Steady-State Subchannel Thermal-Hydraulic Assessment of Advanced Uranium-Based and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors. Nuclear Technology 207:8, pages 1216-1236.
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S. Wang, T. Beuthe, X. Huang, A. Nava Dominguez, A. V. Colton & B. P. Bromley. (2021) Transient System Thermal-Hydraulic Assessment of Advanced Uranium- and Thorium-Based Fuel Bundle Concepts for Potential Use in Pressure Tube Heavy Water Reactors—I: Two-Channel Analyses. Nuclear Technology 207:4, pages 469-493.
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Kohsuke Tsubakihara, Shin Okumura, Chikako Ishizuka, Tadashi Yoshida, Futoshi Minato & Satoshi Chiba. (2021) Evaluation of fission product yields and associated covariance matrices. Journal of Nuclear Science and Technology 58:2, pages 151-165.
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Ashlea V. Colton & Blair P. Bromley. (2018) Simulations of Pressure-Tube–Heavy-Water Reactor Cores Fueled with Thorium-Based Mixed-Oxide Fuels. Nuclear Technology 203:2, pages 146-172.
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Kenichi Tada, Takeo Kikuchi, Takao Sakino & Kenya Suyama. (2018) Analyses of used BWR fuel assay data with the integrated burnup code system SWAT4.0. Journal of Nuclear Science and Technology 55:2, pages 138-150.
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Toru Yamamoto, Tomohiro Sakai & Daiki Iwahashi. (2017) Analysis of measured isotopic compositions by CASMO5 coupled with a JENDL-4.0 base library for irradiated fuel of light water reactors. Journal of Nuclear Science and Technology 54:3, pages 391-403.
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Blair P. Bromley. (2014) High-Utilization Lattices for Thorium-Based Fuels in Heavy Water Reactors. Nuclear Technology 186:1, pages 17-32.
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Toru YAMAMOTO & Munenari YAMAMOTO. (2008) Nuclear Analysis of PIE Data of Irradiated BWR 8×8-2 and 8×8-4 UO2 Fuel Assemblies. Journal of Nuclear Science and Technology 45:11, pages 1193-1214.
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Toru YAMAMOTO & Yuichiro KANAYAMA. (2008) Lattice Physics Analysis of Burnups and Isotope Inventories of U, Pu, and Nd of Irradiated BWR 9×9-9 UO2 Fuel Assemblies. Journal of Nuclear Science and Technology 45:6, pages 547-566.
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