Anticipated Transient Without Scram Analysis of the Simplified Boiling Water Reactor Following Main Steam Isolation Valve Closure with Boron Injection-Reference-Cited by-同舟云学术

Anticipated Transient Without Scram Analysis of the Simplified Boiling Water Reactor Following Main Steam Isolation Valve Closure with Boron Injection

Published:1996-07 Issue:1 Volume:115 Page:22-34
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Khan Hasna J.¹,Cheng Hsiang-Shou¹,Rohatgi Upendra S.¹

Affiliation:

1. Brookhaven National Laboratory Department of Advanced Technology, Upton, New York 11973

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-A35272

Reference3 articles.

1. “SBWR Standard Safety Analysis Report,” 25A5113, Rev. A, General Electric Nuclear Energy (1992).

2. U. S. ROHATGI et al. “Models and Correlations in RAMONA-4B Code,” Brookhaven National Laboratory (internal report in preparation).

3. W. WULFF, H. S. CHENG, D. J. DIAMOND, and M. KHATIB-RAHBAR, “A Description and Assessment of RAMONA-3B MOD.O CYCLE 4: A Computer Code with Three-Dimensional Neutron Kinetics for BWR System Transients,” NUREG/CR-3664, U.S. Nuclear Regulatory Commission (1984).

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