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Journal Articles

Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool, 1; Overview

Kaji, Yoshiyuki; Nemoto, Yoshiyuki; Nagatake, Taku; Yoshida, Hiroyuki; Tojo, Masayuki*; Goto, Daisuke*; Nishimura, Satoshi*; Suzuki, Hiroaki*; Yamato, Masaaki*; Watanabe, Satoshi*

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

In this research program, cladding oxidation model in SFP accident condition, and numerical simulation method to evaluate capability of spray cooling system which was deployed for spent fuel cooling during SFP accident, have been developed. These were introduced into the severe accident codes such as MAAP and SAMPSON, and SFP accident analyses were conducted. Analyses using Computational Fluid Dynamics (CFD) code were conducted as well for the comparison with SA code analyses and investigation of detail in the SFP accident. In addition, three-dimensional criticality analysis method was developed as well, and safer loading pattern of spent fuels in pool was investigated.

Journal Articles

Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs

Takeda, Takeshi; Otsu, Iwao

Nuclear Engineering and Technology, 50(6), p.829 - 841, 2018/08

 Times Cited Count:13 Percentile:79.66(Nuclear Science & Technology)

Journal Articles

Behavior of high-burnup advanced LWR fuels under design-basis accident conditions

Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

Journal Articles

The Effect of oxidation and crystal phase condition on the ballooning and rupture behavior of Zircaloy-4 cladding tube-under transient-heating conditions

Narukawa, Takafumi; Amaya, Masaki

Journal of Nuclear Science and Technology, 53(1), p.112 - 122, 2016/01

 Times Cited Count:7 Percentile:55.03(Nuclear Science & Technology)

Journal Articles

Application of simplified condensation model to PWR LBLOCA transient analysis with TRAC-PF1 code

; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.290 - 297, 1996/04

 Times Cited Count:3 Percentile:32.72(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Assessment of predictive capability of REFLA/TRAC code for peak clad temperature during reflood in LBLOCA of PWR with small scale test, SCTF and CCTF data

; Onuki, Akira; Murao, Yoshio

Validation of Systems Transients Analysis Codes (FED-Vol. 223), 0, 8 Pages, 1995/00

no abstracts in English

JAEA Reports

Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA

Onuki, Akira; ; Iguchi, Tadashi; Murao, Yoshio

JAERI-Research 94-012, 59 Pages, 1994/08

JAERI-Research-94-012.pdf:1.75MB

no abstracts in English

JAEA Reports

JAEA Reports

Assessment of one dimensional reflood model in REFLA/TRAC code

; Onuki, Akira; Murao, Yoshio

JAERI-M 93-240, 83 Pages, 1993/12

JAERI-M-93-240.pdf:1.94MB

no abstracts in English

JAEA Reports

Assessment of TRAC-BF1 1D reflood model with CCTF and SCTF data

; Onuki, Akira; Abe, Yutaka*; Murao, Yoshio

JAERI-M 93-045, 126 Pages, 1993/03

JAERI-M-93-045.pdf:2.56MB

no abstracts in English

JAEA Reports

Assessment of TRAC-PF1/MOD1 code for large break LOCA in PWR

; Onuki, Akira; Abe, Yutaka*; Murao, Yoshio

JAERI-M 93-028, 252 Pages, 1993/03

JAERI-M-93-028.pdf:5.98MB

no abstracts in English

JAEA Reports

Study of two-phase flow under low velocity in PWR-LOCA

Onuki, Akira

JAERI-M 92-150, 134 Pages, 1992/10

JAERI-M-92-150.pdf:4.08MB

no abstracts in English

Journal Articles

BWR loss-of-coolant accident tests at ROSA-III with high temperature emergency core coolant injection

; ; Tasaka, Kanji

Journal of Nuclear Science and Technology, 25(2), p.169 - 179, 1988/02

no abstracts in English

JAEA Reports

Evaluation Report on CCTF-II Reflood Test C2-9(Run 68); Effect of LPCI Flow Rate

; ; *; *; ; Murao, Yoshio

JAERI-M 87-002, 77 Pages, 1987/02

JAERI-M-87-002.pdf:1.54MB

no abstracts in English

JAEA Reports

Evaluation Report on CCTF-II Reflood Test C2-8(Run67); Effect of System Pressure

; ; *; *; ; Murao, Yoshio

JAERI-M 87-001, 83 Pages, 1987/01

JAERI-M-87-001.pdf:1.77MB

no abstracts in English

Journal Articles

Assessment of core thermo-hydrodynamic models of REFLA-1D code with CCTF data for reflood phase of PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 22(12), p.983 - 994, 1985/12

 Times Cited Count:17 Percentile:86.32(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

Evaluation Report on CCTF Core-II Reflood Test C2-6, Run 64; Effect of Radial Power Profile

; ; *; ; ; Murao, Yoshio

JAERI-M 85-027, 88 Pages, 1985/03

JAERI-M-85-027.pdf:1.82MB

no abstracts in English

JAEA Reports

Thermal-Hydrauluc Analysis of Loss-of-Coolant Accident in the JMTR

;

JAERI-M 85-001, 33 Pages, 1985/02

JAERI-M-85-001.pdf:0.74MB

no abstracts in English

41 (Records 1-20 displayed on this page)