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

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The Fort St. Vrain high temperature gas-cooled reactor

Published:1979-06 Issue:1 Volume:53 Page:125-131
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

Reference9 articles.

1. The fort st. vrain high temperature gas-cooled reactor III. Helium circulator auxiliaries

2. Steam Turbine Driven Circulators for High Temperature Gas-Cooled Reactors, Part II: Development;Barbat,1972

3. PSC Pre-Nuclear Pelton Wheel Cavitation Report;Technical Staff,1973

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

Cited by 7 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. Early stage oxidation of ZrC under 10 MeV Au3+ ion-irradiation at 800 °C;Corrosion Science;2020-06

2. Comparing the environmental impacts of uranium- and thorium-based fuel cycles with different recycle options;Progress in Nuclear Energy;2017-09

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

4. The Fort St. Vrain high temperature gas-cooled reactor: VII. Prestressed concrete reactor vessel (PCRV) performance;Nuclear Engineering and Design;1982-09

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

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