Application of code scaling applicability and uncertainty methodology to the large break loss of coolant-Reference-Cited by-同舟云学术

Application of code scaling applicability and uncertainty methodology to the large break loss of coolant

Published:1998-11 Issue:1-2 Volume:186 Page:39-52
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Young M.Y.,Bajorek S.M.,Nissley M.E.,Hochreiter L.E.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference12 articles.

1. Quantifying reactor safety margins—part 1: an overview of the code scaling, applicability, and uncertainty evaluation methodology;Boyack;Nuclear Eng. Des.,1990

2. Boyack, B.E., et al., 1989. Quantifying Reactor Safety Margins, NUREG/CR-5249.

3. TPG response to the foregoing letters-to-the-Editor;Boyack;Nuclear Eng. Des.,1992

4. ECCS, 1987. Compendium of ECCS research for Realistic LOCA Analysis, NUREG–1230.

5. Federal Register, 1988. Emergency Core Cooling Systems: Revisions to Acceptance Criteria. V53, N180, pp. 35996–36005.

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