Investigation of System Responses of the Maanshan Nuclear Power Plant to the Loss of Residual Heat Removal During Midloop Operation Using a RELAP5/MOD3 Simulation-Reference-Cited by-同舟云学术

Investigation of System Responses of the Maanshan Nuclear Power Plant to the Loss of Residual Heat Removal During Midloop Operation Using a RELAP5/MOD3 Simulation

Published:1996-11 Issue:2 Volume:116 Page:160-172
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Ferng Yuh-Ming¹,Ma Shau-Shei¹

Affiliation:

1. Institute of Nuclear Energy Research, P.O. Box 3-3 Lung-Tan, Taiwan 325, Taiwan

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/NT96-A35297

Reference11 articles.

1. J. L. CREWS et al. “Loss of Residual Heat Removal System Diablo Canyon, Unit 2, April 10, 1983,” NUREG-1269, U.S. Nuclear Regulatory Commission (June 1991).

2. “Loss of Vital AC Power and Residual Heat Removal System During Mid-Loop Operations at Vogtle Unit 1 on March 20, 1990,” NUREG-1410, U.S. Nuclear Regulatory Commission (June 1990).

3. “Evaluation of Potential Severe Accidents During Low Power and Shutdown Operation at Surry, Unit 1,” NU-REG/CR-6144, U.S. Nuclear Regulatory Commission (1994).

4. “Thermal-Hydraulic Processed During Reduced Inventory Operation with Loss of Residual Heat Removal,” NU-REG/CR-5855, EGG-2671, Rev. 2, U.S. Nuclear Regulatory Commission (Apr. 1992).

5. R. L. KIANG et al. “Decay Heat Removal Experiments in a UTSG Two-Loop Test Facility,” EPRI No-2621, Electric Power Research Institute (Sep. 1992).

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