Post-accident pressure and temperature transients in a dry containment — A parametric study-Reference-Cited by-同舟云学术

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Post-accident pressure and temperature transients in a dry containment — A parametric study

Published:1966-04 Issue:3 Volume:3 Page:451-466
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Voigt O.

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

Reference10 articles.

1. S. Levy, Prediction of two-phase critical flow rate, ASME-paper 64-HT-8.

2. AEG-KEA-Report no. 392, Post shutdown heat in UO2-fuel (in German).

3. AEG-KEA-Report no. 281, Description of Druckschale-44 computer program (in German).

4. M. Jacob, Heat Transfer, vol. 1, 5th ed. (John Wiley and Sons - Chapman and Hall Ltd.) p. 373.

5. AEG-KEA Report, KWL, calculation of design pressure of the containment (in German).

Cited by 3 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. TECAR, a new program for LOCA analysis;Nuclear Engineering and Design;1977-11

2. ZOCO V, a computer code for the calculation of time- and space-dependent pressure distributions in reactor containments;Nuclear Engineering and Design;1972-12

3. Calculation of maximum equilibrium pressure and temperature inside the containment of a pressurized water reactor following rupture of the primary coolant circuit;Nuclear Engineering and Design;1966-10

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