Evaluation of severe accident risks: Quantification of major input parameters: MAACS (MELCOR Accident Consequence Code System) input

Technical Report · Sat Dec 01 00:00:00 EST 1990

DOI:https://doi.org/10.2172/6360728· OSTI ID:6360728

Sprung, J L; Jow, H-N ^[1]; Rollstin, J A ^[2]; Helton, J C ^[3]

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1. Sandia National Labs., Albuquerque, NM (USA)
2. GRAM, Inc., Albuquerque, NM (USA)
3. Arizona State Univ., Tempe, AZ (USA)

Estimation of offsite accident consequences is the customary final step in a probabilistic assessment of the risks of severe nuclear reactor accidents. Recently, the Nuclear Regulatory Commission reassessed the risks of severe accidents at five US power reactors (NUREG-1150). Offsite accident consequences for NUREG-1150 source terms were estimated using the MELCOR Accident Consequence Code System (MACCS). Before these calculations were performed, most MACCS input parameters were reviewed, and for each parameter reviewed, a best-estimate value was recommended. This report presents the results of these reviews. Specifically, recommended values and the basis for their selection are presented for MACCS atmospheric and biospheric transport, emergency response, food pathway, and economic input parameters. Dose conversion factors and health effect parameters are not reviewed in this report. 134 refs., 15 figs., 110 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USNRC
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6360728
• Report Number(s): NUREG/CR-4551-Vol.2-Rev.1-Pt.7; SAND-86-1309-Vol.2-Rev.1-Pt.7; ON: TI91006095; TRN: 91-002550
• Country of Publication: United States
• Language: English

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