ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor-Reference-Cited by-同舟云学术

ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor

Published:1985-01 Issue:1 Volume:68 Page:77-93
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Tasaka K.¹,Suzuki M.¹,Anoda Y.¹,Koizumi Y.¹,Yonomoto T.¹,Kumamaru H.¹,Nakamura H.¹,Shiba M.¹

Affiliation:

1. Japan Atomic Energy Research Institute 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-A33569

Reference10 articles.

1. L. S. LEE et al. “BWR Blowdown/Emergency Core Cooling Program 64-Rod Bundle Core Spray Interaction (BD/ECC 1A), Final Report, Vol. I, Large Break Simulation Tests,” NUREG/CR-2009-I, EPRI-NP-1782-1, GEAP-24912-1, General Electric Company (1981).

2. W. S. HWANG, “BWR Blowdown/Emergency Core Cooling Program 64-Rod Bundle Core Spray Interaction (BD/ECC1A) Final Report, Vol. II, Small Break Simulation Tests With and Without Degraded ECC,” NUREG/CR-2009-II” EPRI-NP-1782-11, GEAP-24912-II, General Electric Company (1981).

3. ROSA-III Base Test Series for a Large Break Loss-of-Coolant Accident in a Boiling Water Reactor

4. 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).

5. Boiling Water Reactor Loss of Coolant Tests Single Failure Tests with ROSA-III

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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. Core heat transfer analysis during a BWR LOCA simulation experiment at ROSA-III;Nuclear Engineering and Design;1987-08

5. BWR small break LOCA counterpart tests at ROSA-III and FIST test facilities;Nuclear Engineering and Design;1987-06