The Fort St. Vrain high temperature gas-cooled reactor-Reference-Cited by-同舟云学术

The Fort St. Vrain high temperature gas-cooled reactor

Published:1979-06 Issue:1 Volume:53 Page:117-123
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

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

Reference5 articles.

1. Loading of Fuel and Reflector Elements in the Fort St. Vrain Initial Core (Results of Start-up Test A-1);Marshall;GA-A13101, UC-77,1974

2. Fort St. Vrain Initial Fuel Loading and Physics Tests;Asmussen;GA-A13038,1974

3. Fort St. Vrain Start-up Test A-3: Pulsed-Neutron Experiments;Pfeiffer;GA-A13079, UC-77,1974

4. Neutron Flux Distribution Measurements in the Fort St. Vrain Initial Core (Results of Fort St. Vrain Start-up Test A-7);Marshall;GA-A13176, UC-77,1975

5. General Atomic Co. Internal Correspondence;Brown,1974

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1. New approach to handle neutron startup sources in a high temperature gas-cooled reactor;Applied Radiation and Isotopes;1999-11

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

3. Nuclear process heat—application to coal gasification;Nuclear Engineering and Design;1981-09

4. The Fort St. Vrain high temperature gas-cooled reactor;Nuclear Engineering and Design;1980-12

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