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西山　潤 (ニシヤマ　ジュン,NISHIYAMA Jun)

基本情報	研究分野	研究業績	教育業績	社会貢献業績

　

• 論文
• 研究課題

論文
No.	論文タイトル	誌名(出版物名)	巻	号	開始ページ	終了ページ	出版年月	DOI	査読の有無
1	Feasibility of breed-and-burn reactor core design with nitride fuel and lead coolant	Annals of Nuclear Energy	182				2023年	https://doi.org/10.1016/j.anucene.2022.1095831
2	Impact of the Melt-Refining Process on the Performance of Sodium-Cooled Rotational Fuel-Shuffling Breed-and-Burn Reactors	Nuclear Science and Engineering					2023年	https://doi.org/10.1080/00295639.2022.21536391
3	Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor with Nitride Fuel and Sodium Coolant	Nuclear Science and Engineering	197	4			2023年	https://doi.org/10.1080/00295639.2022.21299521
4	Granular fuel debris shape modeling in MPS-DEM for the simulation of fuel debris bed formation in water	Journal of Nuclear Science and Technology	59	4	438	445	2022年04月03日	https://doi.org/10.1080/00223131.2021.19755841
5	Neutron Balance Features in Breed-and-Burn Fast Reactors	Nuclear Science and Engineering	196	3	1	20	2022年03月04日	https://doi.org/10.1080/00295639.2021.19803611
6	Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis	Journal of Nuclear Science and Technology	59	1	1	10	2022年01月02日	https://doi.org/10.1080/00223131.2021.19500681
7	Impact of neutron generation time on released energy in falling fuel debris at supercritical condition	Journal of Nuclear Science and Technology	59	2			2022年	https://doi.org/10.1080/00223131.2021.19633441
8	Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling	Nuclear Science and Engineering	196	1	1	12	2022年	https://doi.org/10.1080/00295639.2021.19510631
9	Characteristics of reactivity change as fuel debris falls in water	Progress in Nuclear Energy	139				2021年	https://doi.org/10.1016/j.pnucene.2021.1038571
10	Optimization of reactor size in the small sodium-cooled CANDLE burning reactor	Annals of Nuclear Energy	153				2021年	https://doi.org/10.1016/j.anucene.2020.1080401
11	Supercritical Transient Analysis for Ramp Reactivity Insertion Using Multiregion Integral Kinetics Code	Nuclear Science and Engineering	195	5			2021年	https://doi.org/10.1080/00295639.2020.18479791
12	Burnup Performance of CANDLE Burning Reactor Using Sodium Coolant	Nuclear Science and Engineering					2020年	https://doi.org/10.1080/00295639.2020.17754331
13	Neutronic modeling of a subcritical system with corium particles and water from international benchmark	Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika	2020	2			2020年	https://doi.org/10.26583/NPE.2020.2.121
14	Radiation Dose Analysis in Criticality Accident of Fuel Debris in Water	Nuclear Science and Engineering	194	3			2020年	https://doi.org/10.1080/00295639.2019.16654591
15	Reactivity Feedback Effect on Supercritical Transient Analysis of Fuel Debris	Nuclear Science and Engineering	194	7			2020年	https://doi.org/10.1080/00295639.2020.17435801
16	Visualization of neutron characteristics distribution of debris particles	Scientific Visualization	12	3			2020年	https://doi.org/10.26583/sv.12.3.091
17	Neutron total cross section measurements of polyethylene using time-of-flight method at KURNS-LINAC	Journal of Nuclear Science and Technology	57	1			2020年	https://doi.org/10.1080/00223131.2019.16478941
18	Effects of compensating for fuel losses during the melt-refining process for a small CANDLE reactor	Annals of Nuclear Energy	135				2020年	https://doi.org/10.1016/j.anucene.2019.1069691
19	Evaluation of Discharged Fuel in Preproposed Breed-and-Burn Reactors from Proliferation, Decay Heat, and Radiotoxicity Aspects	Nuclear Science and Engineering	194	5			2020年	https://doi.org/10.1080/00295639.2019.17063221
20	Concept of breed and burn reactor with spiral fuel shuffling	Annals of Nuclear Energy	127				2019年	https://doi.org/10.1016/j.anucene.2018.12.0061
21	Application of melt-refining process to transition state of CANDLE burning fast reactor	Annals of Nuclear Energy	128				2019年	https://doi.org/10.1016/j.anucene.2018.12.0381
22	Numerical analysis of criticality of fuel debris falling in water	Annals of Nuclear Energy	131				2019年	https://doi.org/10.1016/j.anucene.2019.03.0051
23	Initial core design of CANDLE burning fast reactor using plutonium from LWR spent fuel	Annals of Nuclear Energy	120				2018年	https://doi.org/10.1016/j.anucene.2018.06.0151
24	Design concepts of small CANDLE reactor with melt-refining process	Progress in Nuclear Energy	108				2018年	https://doi.org/10.1016/j.pnucene.2018.05.0191
25	Concept of Stationary Wave Reactor with Rotational Fuel Shuffling	Nuclear Science and Engineering	191	2			2018年	https://doi.org/10.1080/00295639.2018.14637441
26	Potential for the use of a liquid activation circulation material to measure the neutron flux in a high gamma-ray background	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	903				2018年	https://doi.org/10.1016/j.nima.2018.06.0661
27	Applicability of the two-angle differential method to response measurement of neutron-sensitive devices at the RCNP high-energy neutron facility	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	849				2017年	https://doi.org/10.1016/j.nima.2016.12.0311
28	Development of the high-energy neutron fluence rate standard field in Japan with a peak energy of 45 MeV using the 7Li(p,n)7Be reaction at TIARA	Journal of Nuclear Science and Technology	54	5			2017年	https://doi.org/10.1080/00223131.2017.12913741
29	Effects of cooling interval time in melt and refining process for CANDLE burning	Annals of Nuclear Energy	105				2017年	https://doi.org/10.1016/j.anucene.2017.03.0111
30	Spectral measurement of quasi-monoenergetic high-energy neutron field by combination of TOF and Bonner unfolding methods	2015 IEEE Nuclear Science Symposium and Medical Imaging Conference, NSS/MIC 2015					2016年10月03日	https://doi.org/10.1109/NSSMIC.2015.75819081	査読有り
31	Application of melt and refining procedures in the CANDLE reactor concept	Annals of Nuclear Energy	90				2016年	https://doi.org/10.1016/j.anucene.2015.12.0011
32	Time-of-Flight Measurements for Low-Energy Components of 45-MeV Quasi-Monoenergetic High-Energy Neutron Field from 7Li(p n) Reaction	IEEE Transactions on Nuclear Science	62	3			2015年	https://doi.org/10.1109/TNS.2015.24322731
33	Neutron dosimetry in quasi-monoenergetic fields of 244 and 387 MeV	IEEE Transactions on Nuclear Science	60	1			2013年	https://doi.org/10.1109/TNS.2013.22393121
34	Two-dimensional differential calibration method for a neutron dosemeter using a thermal neutron beam	Radiation Protection Dosimetry	155	4			2013年	https://doi.org/10.1093/rpd/nct0291
35	Response measurement of a Bonner sphere spectrometer for high-energy neutrons	IEEE Transactions on Nuclear Science	59	1 PART 2			2012年	https://doi.org/10.1109/TNS.2011.21754061
36	Absolute measurement of activity of 198au foils using the 4πβ-γ coincidence counting method andcorrections by the Monte Carlo simulation	Radiation Protection Dosimetry	148	2			2012年	https://doi.org/10.1093/rpd/ncr0291
37	Quasi-monoenergetic neutron energy spectra for 246 and 389 MeV 7Li(p,n) reactions at angles from 0° to 30°	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	629	1			2011年	https://doi.org/10.1016/j.nima.2010.12.0221
38	Calibration of a Bonner sphere spectrometer in quasi-monoenergetic neutron fields of 244 and 387 MeV	Journal of Instrumentation	6	10			2011年	https://doi.org/10.1088/1748-0221/6/10/P100151
39	The calibration of bonner sphere spectrometer	Radiation Protection Dosimetry	146	1-3			2011年	https://doi.org/10.1093/rpd/ncr1231
40	Feasibility study on using imaging plates to estimate thermal neutron fluence in neutron-gamma mixed fields	Radiation Protection Dosimetry	147	3			2011年	https://doi.org/10.1093/rpd/ncq4931
41	Development of a compact flat response neutron detector	IEEE Transactions on Nuclear Science	58	5 PART 2			2011年	https://doi.org/10.1109/TNS.2011.21631911
42	New idea of a small-sized neutron detector with a plastic fibre	Radiation Protection Dosimetry	146	1-3			2011年	https://doi.org/10.1093/rpd/ncr1191
43	Thermal neutron calibration method using an intense neutron beam from JRR-3M	Radiation Measurements	45	10			2010年	https://doi.org/10.1016/j.radmeas.2010.06.0521
44	Measurements of kev-neutron capture cross sections and capture gamma-ray spectra of 117,119Sn	Journal of Nuclear Science and Technology	45	4			2008年	https://doi.org/10.1080/18811248.2008.97114441
45	Measurements of neutron-capture cross sections of radioactive nuclides through high-energy gamma-ray spectroscopic studies	KURRI Progress Report			125	125	2006年
46	A study on neutron capture cross sections of MA nuclides with γ-γ coincidence method	KURRI Progress Report			124	124	2006年
47	A detection system for (n,n′) reaction studies of astrophysical interest	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	564	1			2006年	https://doi.org/10.1016/j.nima.2006.03.0361
48	New approach for measuring the (n,γ) cross section of a nucleus by a few keV neutron	Journal of the Physical Society of Japan	74	11			2005年	https://doi.org/10.1143/JPSJ.74.29811
49	Epitaxial growth of nanometer-thick CaF2/CdF2 heterostructures using partially ionized beam epitaxy	Solid-State Electronics	42	7-8			1998年	https://doi.org/10.1016/S0038-1101(98)00083-51

　

共同研究・競争的資金等の研究課題
No.	提供機関	制度名	課題名等	資金種別	研究期間
1	日本学術振興会	科学研究費助成事業 挑戦的萌芽研究	原子力電池用放射線源Po-209の特性・製造に関する基礎研究		2014年04月 - 2017年03月
2			‐	競争的資金

　

　

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