Journal of Nuclear Science and Technology, Volume 51, Issue 4 (2014)

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Journal of Nuclear Science and Technology, Volume 51, Issue 4 (2014)

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Quantities of I-131 and Cs-137 in accumulated water in the basements of reactor buildings in process of core cooling at Fukushima Daiichi nuclear power plants accident and its influence on late phase source terms
Fukushima NPP Accident Related
Akihide Hidaka & Jun Ishikawa
Pages: 413-424
Published online: 05 Feb 2014
AbstractforQuantities of I-131 and Cs-137 in accumulated water in the basements of reactor buildings in process of core cooling at Fukushima Daiichi nuclear power plants accident and its influence on late phase source terms | Full Text | References | PDF (1.1 MB)
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Article
Evaluation of neutron nuclear data on antimony isotopes
Keiichi Shibata
Pages: 425-436
Published online: 02 Jan 2014
AbstractforEvaluation of neutron nuclear data on antimony isotopes | Full Text | References | PDF (1.7 MB)
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Article
JSFR key technology evaluation on fuel handling system
Yoshitaka Chikazawa, Atsushi Katoh, Hiroyuki Obata, Masayuki Uzawa, Kazuhiro Koga & Ryo Chishiro
Pages: 437-447
Published online: 07 Jan 2014
AbstractforJSFR key technology evaluation on fuel handling system | Full Text | References | PDF (1.4 MB)
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Article
Prediction of water droplet evaporation on zircaloy surface
Chi Young Lee & Wang Kee In
Pages: 448-456
Published online: 08 Jan 2014
AbstractforPrediction of water droplet evaporation on zircaloy surface | Full Text | References | PDF (647.1 KB)
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Development of extraction chromatographic adsorbent using alkylpyridinedicarboxyamides as extractant for separation of trivalent minor actinides from lanthanides – stability and separation ability against nitric acid exposure and gamma-ray irradiation
Makoto Arisaka, Masayuki Watanabe, Yumi Sugo, Kumiko Kobayashi, Osamu Kanao & Takaumi Kimura
Pages: 457-464
Published online: 07 Jan 2014
AbstractforDevelopment of extraction chromatographic adsorbent using alkylpyridinedicarboxyamides as extractant for separation of trivalent minor actinides from lanthanides – stability and separation ability against nitric acid exposure and gamma-ray irradiation | Full Text | References | PDF (558.7 KB)
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Performance evaluation of a resonance ionization mass spectrometer developed for the FFDL system of fast reactors
Yoshihiro Iwata, Chikara Ito, Hideki Harano & Tetsuo Iguchi
Pages: 465-475
Published online: 07 Jan 2014
AbstractforPerformance evaluation of a resonance ionization mass spectrometer developed for the FFDL system of fast reactors | Full Text | References | PDF (1 MB)
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Article
Development of a hydrogen mordenite sorbent for the capture of krypton from used nuclear fuel reprocessing off-gas streams
Mitchell Greenhalgh, Troy G. Garn & Jack D. Law
Pages: 476-481
Published online: 17 Jan 2014
AbstractforDevelopment of a hydrogen mordenite sorbent for the capture of krypton from used nuclear fuel reprocessing off-gas streams | Full Text | References | PDF (599.2 KB)
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Article
Effect of metal electrode on characteristics of gamma-irradiated silicon carbide detector
Junesic Park, Se Hwan Park, Hee-Sung Shin, Ho-Dong Kim, Jungho Kim, Seung Wook Lee, Seung Kyu Lee & Yong Kyun Kim
Pages: 482-486
Published online: 10 Jan 2014
AbstractforEffect of metal electrode on characteristics of gamma-irradiated silicon carbide detector | Full Text | References | PDF (353.9 KB)
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CO2 corrosion of IG-110 nuclear graphite studied by gas chromatography
Zhen Hu, Zhengcao Li, Dongyue Chen, Wei Miao & Zhengjun Zhang
Pages: 487-492
Published online: 14 Jan 2014
AbstractforCO2 corrosion of IG-110 nuclear graphite studied by gas chromatography | Full Text | References | PDF (336.1 KB)
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Article
A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention
Tohru Suzuki, Kenji Kamiyama, Hidemasa Yamano, Shigenobu Kubo, Yoshiharu Tobita, Ryodai Nakai & Kazuya Koyama
Pages: 493-513
Published online: 20 Jan 2014
AbstractforA scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention | Full Text | References | PDF (7.2 MB)
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Article
A study on selective precipitation of U(VI) by hydrophilic cyclic urea derivatives for development of a reprocessing system based on precipitation method
Tomoya Suzuki, Koichiro Takao, Takeshi Kawasaki, Masayuki Harada, Masanobu Nogami & Yasuhisa Ikeda
Pages: 514-520
Published online: 20 Jan 2014
AbstractforA study on selective precipitation of U(VI) by hydrophilic cyclic urea derivatives for development of a reprocessing system based on precipitation method | Full Text | References | PDF (584.2 KB)
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Article
Designing fault-tolerant real-time computer systems with diversified bus architecture for nuclear power plants
Rajendra Prasad Behera, N. Murali & S.A.V. Satya Murty
Pages: 521-525
Published online: 20 Jan 2014
AbstractforDesigning fault-tolerant real-time computer systems with diversified bus architecture for nuclear power plants | Full Text | References | PDF (264.3 KB)
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Article
Quantitative dynamic reliability evaluation of AP1000 passive safety systems by using FMEA and GO-FLOW methodology
Muhammad Hashim, Hidekazu Yoshikawa, Takeshi Matsuoka & Ming Yang
Pages: 526-542
Published online: 05 Feb 2014
AbstractforQuantitative dynamic reliability evaluation of AP1000 passive safety systems by using FMEA and GO-FLOW methodology | Full Text | References | PDF (1.3 MB)
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Article
Single-phase convective heat transfer enhancement by spacer grids in a rod bundle
Sang-Ki Moon, Jongrok Kim, Seok Cho, Byoung Jae Kim, Jong Kuk Park, Young-Jung Youn & Chul-Hwa Song
Pages: 543-557
Published online: 31 Jan 2014
AbstractforSingle-phase convective heat transfer enhancement by spacer grids in a rod bundle | Full Text | References | PDF (1.6 MB)
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Article
Comparison and sensitivity analysis of the core characteristics of a sodium-cooled fast breeder reactor with 750 MWe output evaluated by JENDL-4.0 and ADJ2000R
Kazuya Ohgama, Shigeo Ohki, Kazuteru Sugino & Tsutomu Okubo
Pages: 558-567
Published online: 11 Feb 2014
AbstractforComparison and sensitivity analysis of the core characteristics of a sodium-cooled fast breeder reactor with 750 MWe output evaluated by JENDL-4.0 and ADJ2000R | Full Text | References | PDF (858.2 KB)
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Article
A study of the generation of 232U in UO2 and MOX fuels
Kento Yamamoto & Keisuke Okumura
Pages: 568-573
Published online: 05 Feb 2014
AbstractforA study of the generation of 232U in UO2 and MOX fuels | Full Text | References | PDF (409.8 KB)
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Corrigendum

Correction
Corrigendum
Page: 574
Published online: 05 Feb 2014
CitationforCorrigendum | Full Text | PDF (53.8 KB)
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