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Volume 59, Issue 3

Journal of Nuclear Science and Technology

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Journal of Nuclear Science and Technology, Volume 59, Issue 3 (2022)

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Journal of Nuclear Science and Technology, Volume 59, Issue 3 (2022)

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Vol 61, 2024 Vol 60, 2023 Volume 59, 2022 Vol 58, 2021 Vol 57, 2020 Vol 56, 2019 Vol 55, 2018 Vol 54, 2017 Vol 53, 2016 Vol 52, 2015 Vol 51, 2014 Vol 50, 2013 Vol 49, 2012 Vol 48, 2011 Vol 47, 2010 Vol 46, 2009 Vol 45, 2008 Vol 44, 2007 Vol 43, 2006 Vol 42, 2005 Vol 41, 2004 Vol 40, 2003 Vol 39, 2002 Vol 38, 2001 Vol 37, 2000 Vol 36, 1999 Vol 35, 1998 Vol 34, 1997 Vol 33, 1996 Vol 32, 1995 Vol 31, 1994 Vol 30, 1993 Vol 29, 1992 Vol 28, 1991 Vol 27, 1990 Vol 26, 1989 Vol 25, 1988 Vol 24, 1987 Vol 23, 1986 Vol 22, 1985 Vol 21, 1984 Vol 20, 1983 Vol 19, 1982 Vol 18, 1981 Vol 17, 1980 Vol 16, 1979 Vol 15, 1978 Vol 14, 1977 Vol 13, 1976 Vol 12, 1975 Vol 11, 1974 Vol 10, 1973 Vol 9, 1972 Vol 8, 1971 Vol 7, 1970 Vol 6, 1969 Vol 5, 1968 Vol 4, 1967 Vol 3, 1966 Vol 2, 1965 Vol 1, 1964

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Invited Review A Decade from Fukushima Daiichi NPP Accident

Ten years of Fukushima Dai-Ichi post-accident research on the degradation phenomenology of the BWR core components

Anton Pshenichnikov, Hiroki Shibata, Takuya Yamashita, Yuji Nagae & Masaki Kurata

Pages: 267-291

Published online: 25 Oct 2021

AbstractforTen years of Fukushima Dai-Ichi post-accident research on the degradation phenomenology of the BWR core components | Full Text | References | PDF (7.7 MB) | EPUB

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Cesium Chemistry in the LWR severe accident and towards the decommissioning of Fukushima Daiichi Nuclear Power Station

Masahiko Osaka, Mélany Gouëllo & Kunihisa Nakajima

Pages: 292-305

Published online: 07 Dec 2021

AbstractforCesium Chemistry in the LWR severe accident and towards the decommissioning of Fukushima Daiichi Nuclear Power Station | Full Text | References | PDF (1.3 MB) | EPUB

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Article

Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid

Naon Chang, Heechul Eun, Seonbyeong Kim, Bumkyung Seo & Yongsoo Kim

Pages: 306-317

Published online: 01 Sep 2021

AbstractforDecontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid | Full Text | References | PDF (6 MB) | EPUB

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Open Access

Article

Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV

Shunsuke Endo, Atsushi Kimura, Shoji Nakamura, Osamu Iwamoto, Nobuyuki Iwamoto, Gerard Rovira, Kazushi Terada, Shin-ichiro Meigo, Yosuke Toh, Mariko Segawa, Makoto Maeda & Masayuki Tsuneyama

Pages: 318-333

Published online: 20 Oct 2021

AbstractforNeutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV | Full Text | References | PDF (5.1 MB) | EPUB

512 Views
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Article

G-HyND: a hybrid nuclear data estimator with Gaussian processes

Hiroki Iwamoto, Osamu Iwamoto & Satoshi Kunieda

Pages: 334-344

Published online: 18 Oct 2021

AbstractforG-HyND: a hybrid nuclear data estimator with Gaussian processes | Full Text | References | PDF (5.8 MB) | EPUB

421 Views
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Article

Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel

Chikashi Suzuki, Kunihisa Nakajima & Masahiko Osaka

Pages: 345-356

Published online: 13 Oct 2021

AbstractforPhase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel | Full Text | References | PDF (7.3 MB) | EPUB

273 Views
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Article

Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants

Kotaro Kubo, Sunghyon Jang, Takata Takashi & Akira Yamaguchi

Pages: 357-367

Published online: 27 Sep 2021

AbstractforQuasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants | Full Text | References | PDF (7.9 MB) | EPUB

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Article

Subcriticality determination methodology during fuel loading of accelerator-driven system

Ryota Katano

Pages: 368-381

Published online: 13 Oct 2021

AbstractforSubcriticality determination methodology during fuel loading of accelerator-driven system | Full Text | References | PDF (7.9 MB) | EPUB

263 Views
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Article

Development of fission gas release model for MOX fuel pellets with treatment of heterogeneous microstructure

Yudai Tasaki, Yutaka Udagawa & Masaki Amaya

Pages: 382-394

Published online: 09 Nov 2021

AbstractforDevelopment of fission gas release model for MOX fuel pellets with treatment of heterogeneous microstructure | Full Text | References | PDF (6.4 MB) | EPUB

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Open Access

Article

Halogenation of used aluminum matrix test reactor fuel – a bench-scale demonstration with surrogate materials

Steven D. Herrmann, Haiyan Zhao, Meng Shi, Matthew M. Jones & Michael N. Patterson

Pages: 395-406

Published online: 13 Oct 2021

AbstractforHalogenation of used aluminum matrix test reactor fuel – a bench-scale demonstration with surrogate materials | Full Text | References | PDF (5.5 MB) | EPUB

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Correction

Page: 407

Published online: 01 Dec 2020

CitationforCorrection | Full Text | PDF (253 KB) | EPUB

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