MHTGR development in the United States-Reference-Cited by-同舟云学术

MHTGR development in the United States

Published:1994-01 Issue:3 Volume:28 Page:265-346
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Williams P.M.,Silady F.A.,Dunn T.D.,Noren R.C.,McEachern D.W.,Dilling D.A.,Berkoe J.M.,Homan F.J.,Mears L.D.,Penfield S.R.,Lidsky L.M.,Yan X.L.,Reid C.L.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference37 articles.

1. Modeling of Fission Product Release from HTR Fuel for Risk Analysis;Bolin;Energy,1991

2. Memorandum to James M. Taylor, “Issues Pertaining to the Advanced Reactor (PRISM, MHTGR, and PIUS) and CANDU 3 Designs and Their Relationship to Current Regulatory Requirements,” July 30, 1993;Chilk,1993

3. Rules for the Design of Alloy 617 Nuclear Components to Very High Temperatures, Fatigue, Fracture, and Risk;Corum;PVP,1991

4. Title 40 Code of Federal Regulations;40 CFR 190,1993

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