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Kazuya Ishii

Observed name: Kazuya ISHII
Institution: Hitachi (Japan)
OpenAlex ID: A5111531959
Neutronic Analysis Code for Fuel Assembly Using a Vectorized Monte Carlo Method
1989 · Yuuichi Morimoto, Hiromi Maruyama, et al. · Nuclear Science and Engineering · 43
Three-Dimensional Direct Response Matrix Method Using a Monte Carlo Calculation
2009 · Kazuya ISHII, Tetsushi HINO, et al. · Journal of Nuclear Science and Technology · 15
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A New Direct Calculation Method of Response Matrices Using a Monte Carlo Calculation
1999 · Masanao MORIWAKI, Kazuya ISHII, et al. · Journal of Nuclear Science and Technology · 14
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BWR Core Simulator Using Three-Dimensional Direct Response Matrix and Analysis of Cold Critical Experiments
2010 · Tetsushi HINO, Kazuya ISHII, et al. · Journal of Nuclear Science and Technology · 11
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Analysis of MISTRAL Experiments with JENDL-3.2
2002 · Tom Yamamoto, Yutaka Iwata, et al. · Journal of Nuclear Science and Technology · 8
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Analysis of High Moderation Full MOX BWR Core Physics Experiments BASALA
2005 · Kazuya ISHII, Yoshihira ANDO, et al. · Transactions of the Atomic Energy Society of Japan · 7
Development of an Advanced Core Analysis System for Boiling Water Reactor Designs
1997 · Hiromi Maruyama, Junichi Koyama, et al. · Nuclear Technology · 7
Analysis of MOX Core Physics Experiments MISTRAL
2003 · Kazuya ISHII, Masahiro TATSUMI, et al. · Transactions of the Atomic Energy Society of Japan · 5
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Improvement of Vectorized Monte Carlo Method for Neutron Transport Analysis
1989 · Kazuya ISHII, Hiromi MARUYAMA, et al. · Journal of Nuclear Science and Technology · 5
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Development of Spectral History and Pin Power Correction Methods for Pin-by-Pin Core Analysis Method Using Three-Dimensional Direct Response Matrix
2010 · Takeshi MITSUYASU, Kazuya ISHII, et al. · Journal of Nuclear Science and Technology · 3
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Reconstruction method of homogenized cross sections
2013 · Kazuya Ishii · Journal of Nuclear Science and Technology · 2
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Analysis of the MOX critical experiments BASALA by pin-by-pin core analysis method using three-dimensional direct response matrix
2012 · Kazuya Ishii, Takeshi Mitsuyasu, et al. · Journal of Nuclear Science and Technology · 2
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Computing Acceleration for a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Method
2011 · Takeshi MITSUYASU, Kazuya ISHII, et al. · Progress in Nuclear Science and Technology · 2
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Development of pin-by-pin core analysis method using three-dimensional direct response matrix
2009 · Kazuya Ishii, T. Hino, et al. · 2
Nuclear analysis method based on current coupling neutron response reconstruction method
2023 · Kazuya Ishii, Tetsushi Hino, et al. · Journal of Nuclear Science and Technology · 1
Criticality control technique development for Fukushima Daiichi fuel debris 20 - Evaluation of Organisation for Economic Co-operation and Development/ Nuclear Energy Agency (OECD)/(NEA) burnup credit criticality benchmark phase III-C using core design code
2016 · Takashi Yoshii, Yosuke Miki, et al. · 1
Analysis of Mixed Oxide Fuel Critical Experiments EPICURE and MISTRAL with Nuclear Analysis Code for BWR
2006 · Kazuya ISHII, Atsushi FUSHIMI, et al. · Transactions of the Atomic Energy Society of Japan · 1
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Applicability of Neutronics Design Calculation Method for Axially Heterogeneous Core of RBWR (Resource-Renewable Boiling Water Reactor)
2022 · Kimihiro Yokoi, Tetsushi Hino, et al. · International Conference on Physics of Reactors (PHYSOR)
Criticality control technique development for Fukushima Daiichi fuel debris 47 - measurement of nuclear reactivity of insoluble absorber by using KUCA test facility
2018 · Yuta Shindo, Kazuya Ishii, et al.
Criticality prevention measures for removal of fuel debris using neutron absorber and its effect on corrosion
2017 · Ryo Ishibashi, Kazuya Ishii, et al.
Criticality control technique development for Fukushima Daiichi fuel debris 37 - methodology for applying insoluble neutron absorbers
2017 · Ryo Ishibashi, Yuta Shindo, et al.
Criticality control technique development for Fukushima Daiichi fuel debris 30 - proposal of a statistical evaluation method for the criticalityof the Fukushima Daiichi Nuclear Power Plants
2017 · Yuichi Morimoto, Masanori Akaike, et al.
Criticality control technique development for Fukushima Dai-ichi Nuclear Power Plant fuel debris 11 - criticality safety evaluation
2015 · Mitsuaki Yamaoka, Kazuya Ishii, et al.
Analysis of Mixed Oxide Fuel Critical Experiments with Neutronics ANalysis Codes for Boiling Water Reactors
2000 · Masashi TAMITANI, Hiromi MARUYAMA, et al. · Journal of Nuclear Science and Technology
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Fuel rod for BWR type reactor and fuel assembly
1990 · Hiromi Maruyama, Yuichi Morimoto, et al.
Works count: 27
Citation count: 129
H-index: 7
I10-index: 4
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