CRAC2. Code System for Calculation of Reactor Accident Consequences

Technical Report · Tue Feb 01 04:00:00 EST 1983

OSTI ID:139141

Ritchie, L T; Johnson, J D; Blond, R M ^[1]

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1. Sandia National Labs., Albuquerque, NM (United States)

The CRAC code system was developed in support of the Reactor Safety Study (WASH-1400) to access the risk from potential accidents at nuclear power plants. CRAC2 was developed to satisfy the need for more realistic consequence estimation techniques to be used for such purposes as site evaluation, emergency planning and response, and general risk assessment and to correct errors which existed in the original CRAC system. CRAC2 includes modification of the atmospheric dispersion model and introduction of a new meteorological sampling technique, a new evacuation model, and new output capabilities.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 139141
• Report Number(s): ESTSC/NRC--000117C000000; CCC--419-B
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
54 ENVIRONMENTAL SCIENCES
99 GENERAL AND MISCELLANEOUS
C CODES
COMPUTER PROGRAM DOCUMENTATION
EMERGENCY PLANS
PARTICULATES
RADIATION DOSES
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT