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Title: Reactor accident consequence analysis code (MACCS)

Conference ·
OSTI ID:5320968

Sandia National Laboratories has been involved in the performance of risk assessments for the US Nuclear Regulatory Commission for more than a decade. As part of this effort, Sandia developed the reactor consequence analysis codes, CRAC2, and more recently, MACCS. CRAC2 is an improved version of CRAC, which was used in the Reactor Safety Study (also known as WASH-1400). MACCS was used in recent risk assessments for five nuclear power plants (NUREG-1150). MACCS incorporates many model improvements over CRAC2. Some of these improvements are discussed. A comparison of results obtained with CRAC2 and MACCS is also presented. 19 refs., 3 tabs.

Research Organization:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USNRC
DOE Contract Number:
AC04-76DP00789
OSTI ID:
5320968
Report Number(s):
SAND-89-1421C; CONF-900246-2; ON: DE90003578; TRN: 90-002509
Resource Relation:
Conference: Health Physics Society midyear topical symposium on risk analysis, Atlantic City, NJ (USA), 5 Feb 1990
Country of Publication:
United States
Language:
English