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Title: Loss-of-coolant accident analyses of the Advanced Neutron Source Reactor

Currently in the conceptual design stage, the Advanced Neutron Source Reactor (ANSR) will operate at a high heat flux, a high mass flux, an a high degree of coolant subcooling. Loss-of-coolant accident (LOCA) analyses using RELAP5 have been performed as part of an early evaluation of ANSR safety issues. This paper discusses the RELAP5 ANSR conceptual design system model and preliminary LOCA simulation results. Some previous studies were conducted for the preconceptual design. 12 refs., 7 figs.
Authors:
;  [1] ;  [2]
  1. (Oak Ridge National Lab., TN (USA))
  2. (Martin Marietta Energy Systems, Inc., Oak Ridge, TN (USA))
Publication Date:
OSTI Identifier:
5288327
Report Number(s):
CONF-911107-4
ON: DE91013691
DOE Contract Number:
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 10-15 Nov 1991
Research Org:
Oak Ridge National Lab., TN (United States)
Sponsoring Org:
DOE; USDOE, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; LOSS OF COOLANT; R CODES; PIPES; RUPTURES; RESEARCH REACTORS; ACCUMULATORS; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DEPRESSURIZATION; EMERGENCY PLANS; HEAT FLUX; HEAT TRANSFER; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RECOMMENDATIONS; RISK ASSESSMENT; STEADY-STATE CONDITIONS; TRANSIENTS; ACCIDENTS; COMPUTER CODES; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FAILURES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION; TANKS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors; 990200 -- Mathematics & Computers