The Fort St. Vrain high temperature gas-cooled reactor: VII. Prestressed concrete reactor vessel (PCRV) performance-Reference-Cited by-同舟云学术

The Fort St. Vrain high temperature gas-cooled reactor: VII. Prestressed concrete reactor vessel (PCRV) performance

Published:1982-09 Issue:2 Volume:72 Page:111-123
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Olson H.G.,Brey H.L.,Swart F.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

Reference14 articles.

1. System II Description, Prestressed Concrete Reactor Vessel and Subsystems,1969

2. System 46 Description, Reactor Plant Cooling Water System,1974

3. The Fort St. Vrain Prestressed Concrete Reactor Vessel — Progress of Construction;Peinado,1969

4. H.G. Olson, H.L. Brey, F.E. Swart and D. Warembourg, The Fort St. Vrain high temperature gas-cooled reactor: X, Core temperature fluctuations, next article in this issue.

5. Final Safety Analysis Report (FSAR), Fort St. Vrain High Temperature Gas-Cooled Reactor.

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