The Fort St. Vrain high temperature gas-cooled reactor: XIII. Radiological and shielding performance of Fort St. Vrain-Reference-Cited by-同舟云学术

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The Fort St. Vrain high temperature gas-cooled reactor: XIII. Radiological and shielding performance of Fort St. Vrain

Published:1982-09 Issue:2 Volume:72 Page:147-152
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Brey H.L.,Olson H.G.

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

Reference11 articles.

1. Comparison of radioactive materials released from the Fort St. Vrain HTGR and LWRs;Brey;Health Phys.,1981

2. The Fort St. Vrain high temperature gas-cooled reactor: VII, prestressed concrete reactor vessel (PCRV) performance;Olson;Nucl. Engrg. Des.,1982

3. The Fort St. Vrain Nuclear Generating Station,1974

4. The Fort St. Vrain high temperature gas-cooled reactor

5. Occupational Radiation Exposure at Commercial Nuclear Power Reactors 1979;Brooks;US NRC, NUREG-0713,1981

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. An overview of high-temperature gas-cooled reactors;Nuclear Power Reactor Designs;2024

2. A review and safety aspects of modular high‐temperature gas‐cooled reactors;International Journal of Energy Research;2020-12-16

3. HTGR experience, programs, and future applications;Nuclear Engineering and Design;1982-09

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