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Ball, S.J.; Conklin, J.C.; Harrington, R.M.; Cleveland, J.C.; Clapp, N.E. Jr.
Third Japan-US seminar on HTGR safety technology: proceedings. Volume I1982
Third Japan-US seminar on HTGR safety technology: proceedings. Volume I1982
AbstractAbstract
[en] The Oak Ridge National Laboratory (ORNL) safety analysis program for the HTGR includes development and verification of system response simulation codes, and applications of these codes to specific Fort St. Vrain reactor licensing problems. Licensing studies addressed the oscillation problems and the concerns about large thermal stresses in the core support blocks during a postulated accident
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Brookhaven National Lab., Upton, NY (USA); p. 215-230; 1982; p. 215-230; 3. Japan/US HTGR safety technology seminar; Upton, NY (USA); 2-3 Jun 1982; Available from NTIS, PC A14/MF A01; 1 - GPO as DE84000514
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