The helium purification system of the HTR-10-Reference-Cited by-同舟云学术

The helium purification system of the HTR-10

Published:2002-10 Issue:1-3 Volume:218 Page:163-167
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Yao M.S.,Wang R.P.,Liu Z.Y.,He X.D.,Li J.

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

Reference4 articles.

1. Anon, 1978. Fort St. Vrain experience EM DASH PHASE 2, core physics testing. Electric Power Research Institute (Report) EPRI NP n 698 pp. 135.

2. Kuzmycz, G., 1974. Helium usage in large, high temperature-gas cooled reactors. American Society for Testing and Materials, Book of ASTM Standards 2–4 October 1973 Scholium Int. (Appl. Cryog Technol., vol. 6) pp. 157–175.

3. Olson, H.G., Brey, H.L., Swart, F.E., 1980. Fort St. Vrain high temperature gas-cooled reactor-6 evaluation and removal of primary coolant contaminants, Nucle. Eng. Design 61 (3) 315–322 0029-5493.

4. Shimomura, H., Kawamura, H., Okamoto, Y., Nakano, T., Hagiwara, T., Minami, R., 1974. Thermal and hydraulic performance of high temperature helium gas loop. American Society of Mechanical Engineers (Paper) n 74-WA/HT-3 pp. 8.

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