A method of predicting the temperature response of ballooning fuel rod cladding for PWR LOCA conditions-Reference-Cited by-同舟云学术

A method of predicting the temperature response of ballooning fuel rod cladding for PWR LOCA conditions

Published:1982-10 Issue:3 Volume:72 Page:391-409
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ardron K.H.,Fairbairn S.A.

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

Reference27 articles.

1. Code of Federal Regulations, 10 CFR 50;USNRC,1978

2. Evaluation of simulated LOCA tests that produced large fuel clad ballooning;Powers;US NRC Report NUREG-0536,1979

3. An improved thermal hydraulic analysis method for rod bundle cores;Chelemer;Nucl. Eng. Des.,1977

4. COBRA IIIc a digital computer program for steady state and transient thermohydraulic analysis of rod bundle nuclear fuel elements;Rowe;Battelle Pacific NW Lab. Report No. BNWL-1695,1973

5. MABEL-2: a code to analyse cladding deformation in a loss of coolant accident: status February 1980;Bowring;UKAEA Report AEEW-M 1766,1980

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2. Ballooning in fuel clad: The first of its kind approach for its investigation in fast reactors;International Journal of Pressure Vessels and Piping;2018-02

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4. Exact solution to the conjugate problem of nonuniform cooling of fuel rods;International Journal of Heat and Fluid Flow;1991-06

5. Studies on the Effects of Blockage Upon LWR Emergency Core Cooling Systems;Safety of Thermal Water Reactors;1985