鈴木　徹 (スズキ　トオル,SUZUKI Tohru)

基本情報	研究分野	研究業績	教育業績	社会貢献業績

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	Improvement of solidification model and analysis of 3D channel blockage with MPS method	Frontiers in Energy	15	4	946	958	2021年12月	https://doi.org/10.1007/s11708-021-0754-z1	査読有り
2	Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor	Nuclear Engineering and Technology	53	12	3930	3943	2021年12月	https://doi.org/10.1016/j.net.2021.06.0181	査読有り
3	Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor	Journal of Nuclear Science and Technology	58	3	347	360	2021年03月	https://doi.org/10.1080/00223131.2020.18389641	査読有り
4	Numerical simulation of the solid particle sedimentation and bed formation behaviors using a hybrid method	Energies	13	19			2020年10月	https://doi.org/10.3390/en131950181	査読有り
5	Sedimentation behavior of mixed solid particles	Journal of Nuclear Science and Technology	55	6	623	633	2018年06月03日	https://doi.org/10.1080/00223131.2017.14198881	査読有り
6	Experimental study on debris bed characteristics for the sedimentation behavior of solid particles used as simulant debris	Annals of Nuclear Energy	111		474	486	2018年01月	https://doi.org/10.1016/j.anucene.2017.09.0111	査読有り
7	Numerical simulation of solid-particle sedimentation behaviorusing a multi-fluid model coupled with Dem	17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017	2017-September				2017年01月01日		査読有り
8	Fundamental experiments of jet impingement and fragmentation simulating the fuel relocation in the core disruptive accident of sodium-cooled fast reactors	2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings					2017年01月01日		査読有り
9	SAS4A analysis study on the initiating phase of atws events for generation-IV loop-type SFR	2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings					2017年01月01日		査読有り
10	Two-phase flow measurements in a simulated debris bed	17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017	2017-September				2017年		査読有り
11	Measurements of two-phase pressure drop in a simulated debris bed	International Conference on Nuclear Engineering, Proceedings, ICONE	9				2017年	https://doi.org/10.115/ICONE25-679271	査読有り
12	A new empirical model for self-leveling behavior of cylindrical particle beds	Journal of Nuclear Science and Technology	53	5	713	725	2016年05月03日	https://doi.org/10.1080/00223131.2015.11262041	査読有り
13	Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors	Journal of Nuclear Science and Technology	53	5	698	706	2016年05月03日	https://doi.org/10.1080/00223131.2016.11434091	査読有り
14	Validation study in SAS4A code in simulated mild TOP condition	Transactions of the American Nuclear Society	115		1597	1598	2016年01月01日		査読有り
15	Preliminary analysis of the post-disassembly expansion phase and structural response under unprotected loss of flow accident in prototype sodium cooled fast reactor	International Conference on Nuclear Engineering, Proceedings, ICONE	2				2016年	https://doi.org/10.1115/ICONE24-608931	査読有り
16	Evaluation of recriticality behavior in the material-relocation phase for Japan sodium-cooled fast reactor	Journal of Nuclear Science and Technology	52	11	1448	1459	2015年11月02日	https://doi.org/10.1080/00223131.2015.10057191	査読有り
17	A preliminary evaluation of unprotected loss-of-flow accident for a prototype fast-breeder reactor	Nuclear Engineering and Technology	47	3	240	252	2015年04月	https://doi.org/10.1016/j.net.2015.03.0011	査読有り
18	A numerical study on local fuel-coolant interactions in a simulated molten fuel pool using the SIMMER-III code	Annals of Nuclear Energy	85		740	752	2015年03月25日	https://doi.org/10.1016/j.anucene.2015.06.0301	査読有り
19	SIMMER-III analyses of local fuel-coolant interactions in a simulated molten fuel pool: Effect of coolant quantity	Science and Technology of Nuclear Installations	2015				2015年01月14日	https://doi.org/10.1155/2015/9643271	査読有り
20	First analysis of local fuel-coolant interactions in a molten pool by SIMMER-III using reactor materials	International Conference on Nuclear Engineering, Proceedings, ICONE	2015-January				2015年		査読有り
21	An investigation on debris bed self-leveling behavior with non-spherical particles	Journal of Nuclear Science and Technology	51	9	1096	1106	2014年09月02日	https://doi.org/10.1080/00223131.2014.9104781	査読有り
22	The effect of coolant quantity on local fuel-coolant interactions in a molten pool	Annals of Nuclear Energy	75		20	25	2014年08月19日	https://doi.org/10.1016/j.anucene.2014.07.0421	査読有り
23	An experimental study on local fuel-coolant interactions by delivering water into a simulated molten fuel pool	Nuclear Engineering and Design	275		133	141	2014年08月	https://doi.org/10.1016/j.nucengdes.2014.05.0031	査読有り
24	Numerical study on sedimentation behavior of solid particles used as simulant fuel debris	Journal of Nuclear Science and Technology	51	5	681	699	2014年05月04日	https://doi.org/10.1080/00223131.2014.8874811	査読有り
25	A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention	Journal of Nuclear Science and Technology	51	4	493	513	2014年04月	https://doi.org/10.1080/00223131.2013.8774051	査読有り
26	Evaluation of debris bed self-leveling behavior: A simple empirical approach and its validations	Annals of Nuclear Energy	63		188	198	2014年01月	https://doi.org/10.1016/j.anucene.2013.07.0501	査読有り
27	Development of an evaluation methodology for the fuelrelocation into the coolant plenum in the core disruptive accident of sodium-cooled fast reactors	International Conference on Nuclear Engineering, Proceedings, ICONE	3				2014年	https://doi.org/10.1115/ICONE22-303451	査読有り
28	Safety evaluation of prototype fast-breeder reactor -Analysis of ULOF accident to demonstrate in-vessel retention	International Conference on Nuclear Engineering, Proceedings, ICONE	6				2014年	https://doi.org/10.1115/ICONE22-306041	査読有り
29	Characteristics of pressure buildup from local fuel-coolant interactions in a simulated molten fuel pool	International Conference on Nuclear Engineering, Proceedings, ICONE	2B				2014年	https://doi.org/10.1115/ICONE22-312211	査読有り
30	An experimental investigation on self-leveling behavior of debris beds using gas-injection	Experimental Thermal and Fluid Science	48		110	121	2013年07月	https://doi.org/10.1016/j.expthermflusci.2013.02.0141	査読有り
31	Characteristics of self-leveling behavior of debris beds in a series of experiments	Nuclear Engineering and Technology	45	3	323	334	2013年06月	https://doi.org/10.5516/NET.02.2012.0681	査読有り
32	Empirical correlations for predicting the self-leveling behavior of debris bed	Nuclear Science and Techniques	24	1			2013年02月20日		査読有り
33	Safety design and evaluation in a large-scale Japan sodium-cooled fast reactor	Science and Technology of Nuclear Installations	2012				2012年	https://doi.org/10.1155/2012/6149731	査読有り
34	Experimental studies and empirical models for the transient self-leveling behavior in debris bed	Journal of Nuclear Science and Technology	48	10	1327	1336	2011年10月	https://doi.org/10.3327/jnst.48.13271	査読有り
35	Experimental investigation of bubbling in particle beds with high solid holdup	Experimental Thermal and Fluid Science	35	2	405	415	2011年02月	https://doi.org/10.1016/j.expthermflusci.2010.11.0031	査読有り
36	Experimental investigation on self-leveling behavior in debris beds	Nuclear Engineering and Design	241	1	366	377	2011年01月	https://doi.org/10.1016/j.nucengdes.2010.11.0131	査読有り
37	A Simple Approach to the Prediction of Transient Self-Leveling Behavior of Debris Bed	PROCEEDINGS OF ISHTEC2012, 4TH INTERNATIONAL SYMPOSIUM ON HEAT TRANSFER AND ENERGY CONSERVATION			406	410	2011年		査読有り
38	Self-leveling onset criteria in debris beds	Journal of Nuclear Science and Technology	47	4	384	395	2010年04月	https://doi.org/10.1080/18811248.2010.97119691	査読有り
39	Evaluation of a steam generator tube rupture accident in an accelerator driven system with lead cooling	Progress in Nuclear Energy	50	2-6	363	369	2008年03月	https://doi.org/10.1016/j.pnucene.2007.11.0181	査読有り
40	The SIMMER safety code system and its validation efforts for fast reactor application	International Conference on the Physics of Reactors 2008, PHYSOR 08	3		2370	2378	2008年		査読有り
41	Analyses of transients for an 800 MW-class accelerator driven transmuter with fertile-free fuels	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	562	2	863	866	2006年06月23日	https://doi.org/10.1016/j.nima.2006.02.0731	査読有り
42	Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code	Nuclear Engineering and Design	235	24	2594	2611	2005年12月	https://doi.org/10.1016/j.nucengdes.2005.06.0121	査読有り
43	Application of high frame-rate neutron radiography to liquid-metal two-phase flow research	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	542	1-3	168	174	2005年04月21日	https://doi.org/10.1016/j.nima.2005.01.0951	査読有り
44	Measurements of liquid-metal two-phase flow by using neutron radiography and electrical conductivity probe	Experimental Thermal and Fluid Science	29	3	323	330	2005年03月	https://doi.org/10.1016/j.expthermflusci.2004.05.0091	査読有り
45	Velocity field measurement in gas-liquid metal two-phase flow with use of PIV and neutron radiography techniques	Applied Radiation and Isotopes	61	4	683	691	2004年10月	https://doi.org/10.1016/j.apradiso.2004.03.1101	査読有り
46	Source and reactivity perturbations in accelerator driven systems with conventional MOX and advanced fertile free fuels	Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments			2023	2031	2004年		査読有り
47	Safety aspects of oxide fuels for transmutation and utilization in accelerator driven systems	Journal of Nuclear Materials	320	1-2	147	155	2003年07月01日	https://doi.org/10.1016/S0022-3115(03)00182-X1	査読有り
48	Analysis of gas-liquid metal two-phase flows using a reactor safety analysis code SIMMER-III	Nuclear Engineering and Design	220	3	207	223	2003年04月	https://doi.org/10.1016/S0029-5493(02)00349-71	査読有り
49	Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Theoretical modeling and basic verification	Nuclear Engineering and Design	220	3	224	239	2003年04月	https://doi.org/10.1016/S0029-5493(02)00351-51	査読有り
50	Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Extended verification using multi-bubble condensation experiment	Nuclear Engineering and Design	220	3	240	254	2003年04月	https://doi.org/10.1016/S0029-5493(02)00350-31	査読有り
51	Analyses of unprotected transients in the lead/bismuth-cooled accelerator driven system PDS-XADS	Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy			1725	1732	2003年		査読有り
52	Unprotected transients in a small scale accelerator driven system	International Meeting on Nuclear Applications of Accelerator Technology: Accelerator Application in a Nuclear Renaissance			677	683	2003年

MISC
No.	MISCタイトル	誌名	巻	号	開始ページ	終了ページ	出版年月(日)
1	A methodological study on extending an empirical model to predict self-leveling behavior of debris beds with non-spherical particles	International Conference on Power Engineering 2013, ICOPE 2013					2013年01月01日
2	Experimental evaluation of debris bed characteristics in particulate debris sedimentation behaviour	International Conference on Nuclear Engineering, Proceedings, ICONE	6				2013年01月01日
3	Recent knowledge from an experimental investigation on self-leveling behavior of debris bed	International Conference on Nuclear Engineering, Proceedings, ICONE	4				2013年01月01日
4	Numerical simulation of the self-leveling phenomenon by modified SIMMER-III	International Conference on Nuclear Engineering, Proceedings, ICONE	5	1	751	760	2012年01月01日
5	Experimental study of bubble behavior in a two-dimensional particle bed with high solid holdup	International Conference on Nuclear Engineering, Proceedings, ICONE	4	PARTS A AND B	697	704	2010年12月01日
6	燃料デブリベッドの運動特性に関する基礎的研究―平成19年度研究報告―	日本原子力研究開発機構JAEA-Research			60P		2009年05月
7	Development of severe accident evaluation technology (Level 2 PSA) for sodium-cooled fast reactors (1) overview of evaluation methodology development	International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009	2		1110	1119	2009年01月01日
8	ICONE15-10462 SIMMER-III : A COUPLED NEUTRONICS-THERMOHYDRAULICS COMPUTER CODE FOR SAFETY ANALYSIS	Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE	2007	15	"ICONE1510462	1"-"ICONE1510462-9"	2007年04月22日
9	Measurements of Interfacial Area Concentration in Liquid-Metal Two-Phase Flow	oc. 2004 Jpn.-US Seminar Two-Phase Flow Dynamics			0	0	2004年
10	Advanced modeling of multicomponent vaporization/condensation phenomena for a reactor safety analysis code SIMMER-III	International Conference on Nuclear Engineering, Proceedings, ICONE	3		351	358	2002年10月19日

講演・口頭発表等
No.	講演・口頭発表タイトル	会議名	発表年月日	主催者	開催地
1	Preliminary analysis of the post-disassembly expansion phase and structural response under unprotected loss of flow accident in prototype sodium cooled fast reactor	International Conference on Nuclear Engineering, Proceedings, ICONE	2016年01月01日
2	First analysis of local fuel-coolant interactions in a molten pool by SIMMER-III using reactor materials	International Conference on Nuclear Engineering, Proceedings, ICONE	2015年01月01日
3	Development of an evaluation methodology for the fuelrelocation into the coolant plenum in the core disruptive accident of sodium-cooled fast reactors	International Conference on Nuclear Engineering, Proceedings, ICONE	2014年01月01日
4	Characteristics of pressure buildup from local fuel-coolant interactions in a simulated molten fuel pool	International Conference on Nuclear Engineering, Proceedings, ICONE	2014年01月01日
5	Safety evaluation of prototype fast-breeder reactor -Analysis of ULOF accident to demonstrate in-vessel retention	International Conference on Nuclear Engineering, Proceedings, ICONE	2014年01月01日
6	A methodological study on extending an empirical model to predict self-leveling behavior of debris beds with non-spherical particles	International Conference on Power Engineering 2013, ICOPE 2013	2013年01月01日
7	Recent knowledge from an experimental investigation on self-leveling behavior of debris bed	International Conference on Nuclear Engineering, Proceedings, ICONE	2013年01月01日
8	Experimental evaluation of debris bed characteristics in particulate debris sedimentation behaviour	International Conference on Nuclear Engineering, Proceedings, ICONE	2013年01月01日
9	Numerical simulation of the self-leveling phenomenon by modified SIMMER-III	International Conference on Nuclear Engineering, Proceedings, ICONE	2012年01月01日
10	Experimental study of bubble behavior in a two-dimensional particle bed with high solid holdup	International Conference on Nuclear Engineering, Proceedings, ICONE	2010年12月01日
11	Development of severe accident evaluation technology (Level 2 PSA) for sodium-cooled fast reactors (1) overview of evaluation methodology development	International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009	2009年01月01日
12	The SIMMER safety code system and its validation efforts for fast reactor application	International Conference on the Physics of Reactors 2008, PHYSOR 08	2008年01月01日
13	Analyses of transients for an 800 MW-class accelerator driven transmuter with fertile-free fuels	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	2006年06月23日
14	Application of high frame-rate neutron radiography to liquid-metal two-phase flow research	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment	2005年04月21日
15	Analyses of unprotected transients in the lead/bismuth-cooled accelerator driven system PDS-XADS	Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy	2003年12月01日
16	Advanced modeling of multicomponent vaporization/condensation phenomena for a reactor safety analysis code SIMMER-III	International Conference on Nuclear Engineering, Proceedings, ICONE	2002年10月19日