Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident-Reference-Cited by-同舟云学术

Analyses of ROSA-III Break Area Spectrum Experiments on a Boiling Water Reactor Loss-of-Coolant Accident

Published:1985-12 Issue:3 Volume:71 Page:628-643
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Tasaka K.¹,Koizumi Y.¹,Kukita Y.¹,Nakamura H.¹,Anoda Y.¹,Iriko M.¹,Kumamaru H.¹,Suzuki M.¹

Affiliation:

1. Japan Atomic Energy Research Institute, Department of Nuclear Safety Research Tokai-mura, Naka-gun, Ibaraki-ken, 319-11, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT85-A33685

Reference16 articles.

1. Y. ANODA, K. TASAKA, H. KUMAMARU and M. SHIBA, “ROSA-III System Description for Fuel Assembly No. 4,” JAERI-M 9363, Japan Atomic Energy Research Institute (1981).

2. W. S. HWANG et al. “BWR Blowdown/Emergency Core Cooling Program–64-Rod Bundle Blowdown Heat Transfer (8x8 BDHT) Final Report,” GEAP-NUREG-23977, General Electric Company (1978).

3. R. MURALIDHARAN, E. J. RASTOR and G. W. BURENTTE et al. “BWR Blowdown Heat Transfer Final Report,” GEAP-21214, General Electric Company (1976).

4. A. G. STEPHENS, “BWR Full Integral Simulation Program, FIST Facility Description Report,” NUREG/CR2576, EPRI NP 2314, GEAP-22054, General Electric Company (1982).

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1. BWR Loss-of-Coolant Accident Tests at ROSA-III with High Temperature Emergency Core Coolant Injection;Journal of Nuclear Science and Technology;1988-02

2. INVESTIGATION OF EFFECT OF PRESSURE CONTROL-SYSTEM ON BWR LOCA PHENOMENA USING ROSA-III TEST FACILITY;J NUCL SCI TECHNOL;1987

3. Investigation of Effect of Pressure Control System on BWR LOCA Phenomena Using ROSA-III Test Facility;Journal of Nuclear Science and Technology;1987-10

4. ASSESSMENT OF SAFER03 CODE USING ROSA-III BREAK AREA SPECTRUM TESTS ON BOILING WATER-REACTOR LOSS-OF-COOLANT ACCIDENTS;J NUCL SCI TECHNOL;1987

5. Assessment of SAFER03 Code Using ROSA-III Break Area Spectrum Tests on Boiling Water Reactor Loss-of-Coolant Accidents;Journal of Nuclear Science and Technology;1987-08