Calculation of tube degradation induced by dryout instability in sodium-heated steam generators-Reference-Cited by-同舟云学术

Calculation of tube degradation induced by dryout instability in sodium-heated steam generators

Published:1977-04 Issue:2 Volume:41 Page:181-191
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chiang T.,France D.M.,Bump T.R.

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

Reference14 articles.

1. Thermal Stress Techniques in the Nuclear Industry;Zudans,1965

2. ASME Boiler and Pressure Vessel Code, Section III-Division I, Rules for Construction of Nuclear Power Plant Components, Subsection NA, General Requirements,1974

3. British Institute of Chemical Engineers Symposium;Chojnowski,1974

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