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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:6 Percentile:72.04(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:4 Percentile:45.9(Nuclear Science & Technology)

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

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:86.9(Nuclear Science & Technology)

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

JAEA Reports

Study of the Thermo-Hydrodynamic Phenomena in the Nuclear Core During Reflood Phase

Murao, Yoshio

JAERI-M 83-032, 176 Pages, 1983/03

JAERI-M-83-032.pdf:5.15MB

no abstracts in English

Journal Articles

Analysis of direct contact condensation of flowing steam onto injected water with a multifluid model of two-phase flow

; Kozawa, Yoshiyuki*; *; *

Journal of Nuclear Science and Technology, 20(12), p.1006 - 1022, 1983/00

 Times Cited Count:8 Percentile:69.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

CCTF Core I Test Results

Murao, Yoshio; ; ; ; ; ;

JAERI-M 82-073, 31 Pages, 1982/07

JAERI-M-82-073.pdf:0.92MB

no abstracts in English

JAEA Reports

Journal Articles

Experimental modeling of core hydrodynamics during reflood phase of LOCA

Murao, Yoshio;

Journal of Nuclear Science and Technology, 19(8), p.613 - 627, 1982/00

 Times Cited Count:21 Percentile:87.2(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experimental study of system behaivior during reflood phase of PWR-LOCA using CCTF

Murao, Yoshio; ; ;

Journal of Nuclear Science and Technology, 19(9), p.705 - 719, 1982/00

 Times Cited Count:34 Percentile:93.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of computer code PRECIP-II for calculation of Zr-steam reaction; Comparison of calculation with experiments in temperature transient

;

Journal of Nuclear Science and Technology, 17(4), p.291 - 300, 1980/00

 Times Cited Count:6 Percentile:58.95(Nuclear Science & Technology)

no abstracts in English

Journal Articles

An Analysis of transients in experiments on loss-of-coolant accidents

Nuclear Science and Engineering, 60(1), p.10 - 18, 1976/01

 Times Cited Count:6

no abstracts in English

Journal Articles

High speed two-phase flow, 4; Two-phase discharge coefficient of large sharp-edged orifice

Nihon Genshiryoku Gakkai-Shi, 16(6), p.322 - 329, 1974/06

no abstracts in English

19 (Records 1-19 displayed on this page)
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