Analysis of the Coolant Expansion Due to a Loss-of-Coolant Accident in a Pressurized Water, Nuclear Power Plant-Reference-Cited by-同舟云学术

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Analysis of the Coolant Expansion Due to a Loss-of-Coolant Accident in a Pressurized Water, Nuclear Power Plant

Published:1959-09 Issue:3 Volume:6 Page:238-244
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Harris Tedric A.¹

Affiliation:

1. Westinghouse Electric Corporation, Bettis Atomic Power Laboratory, Pittsburgh, Pennsylvania

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE59-A25665

Reference6 articles.

1. R. D. LYLE, “Efficient Use of Steam,” His Majesty’s Stationery Office, London, 1947.

2. L. S. MARKS, “Mechanical Engineer’s Handbook,” 5th ed., p. 335. McGraw-Hill, New York, 1951.

3. PWR Hazards Summary Report. Westinghouse Electric Corp. WAPD-SC-541 (1957).

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Modeling the transient outlet pressure and mass flow during flashing of HCFC-22 in a small nonadiabatic vessel;Mathematical and Computer Modelling;1999-04

2. Numerical Study of Depressurization Rate during Blowdown Based on Lumped Model Analysis;Journal of Nuclear Science and Technology;1984-12

3. NUMERICAL STUDY OF DEPRESSURIZATION RATE DURING BLOWDOWN BASED ON LUMPED MODEL ANALYSIS;J NUCL SCI TECHNOL;1984

4. Discussion: “Maximum Two-Phase Vessel Blowdown From Pipes” (Moody, F. J., 1966, ASME J. Heat Transfer, 88, pp. 285–294);Journal of Heat Transfer;1966-08-01

5. A Digital Computer Analysis of Loss-of-Coolant Accident for a Multicircuit Core Nuclear Power Plant;Nuclear Science and Engineering;1962-11

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