CRAC2. Code System for Calculation of Reactor Accident Consequences
Technical Report
·
OSTI ID:139082
- Sandia National Labs., Albuquerque, N.M. (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:
- 139082
- Report Number(s):
- ESTSC/NRC--000117I303300; CCC--419-A
- Country of Publication:
- United States
- Language:
- English
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