Simulation of Loss of RHR During Midloop Operations and the Role of Steam Generators in Decay Heat Removal Using the RELAP5/MOD3 Code-Reference-Cited by-同舟云学术

Simulation of Loss of RHR During Midloop Operations and the Role of Steam Generators in Decay Heat Removal Using the RELAP5/MOD3 Code

Published:1993-09 Issue:3 Volume:103 Page:310-319
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Hassan Yassin A.¹,Raja Laxminarayan L.¹

Affiliation:

1. Texas A&M University, Department of Nuclear Engineering College Station, Texas 77843-3133

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/NT93-A34854

Reference6 articles.

1. J. L. CREWS et al. “Loss of Residual Heat Removal System Diablo Canyon, Unit 2, April 10, 1987 (Augmented Inspection Team Report),” NUREG-1269, U.S. Nuclear Regulatory Commission (June 1991).

2. Core Boiling During Midloop Operation

3. T. S. ANDREYCHEK et al. “Loss of RHRS Cooling While the RCS is Partially Filled,” WCAP-11916, Westinghouse Electric Corporation (July 1988).

4. V. H. RANSOM et al. “RELAP5/MOD3 Code Manual, Volumes 1 and 2,” NUREG/CR-4312, EGG-2396, EG&G Idaho, Inc. (Aug. and Dec. 1985).

5. L. L. RAJA, “Simulation of Condensation Systems in the Presence of Noncondensable Gases,” MS Thesis, Texas Ai&M University (May 1992).

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