MELCOR accident consequence code system (MACCS)

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:5789361

Alpert, D J; Chanin, D I; Helton, J C; Ostmeyer, R M; Ritchie, L T

Currently, the usefulness of reactor accident consequence assessments for providing guidance for planning and decision making is limited by the poor definition of uncertainties in predicted results. The MELCOR Accident Consequence Code System has been structured to facilitate performing uncertainty and sensitivity analyses. MACCS incorporates improved modeling capabilities in the treatment of variable or long duration releases, deposition modeling, dosimetry, emergency response, radiological health effects, and economic effects. At this writing (March 1985), the new code system has been completed and is undergoing testing, de-bugging, etc. Release of the first version of the full MELCOR code system, with associated documentation, is anticipated for the Autumn of 1985.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5789361
• Report Number(s): SAND-85-0884C; CONF-850471-1; ON: DE85009712
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
DOSIMETRY
ECONOMIC ANALYSIS
ECONOMICS
ENVIRONMENTAL TRANSPORT
FISSION PRODUCT RELEASE
HAZARDS
HEALTH HAZARDS
M CODES
MASS TRANSFER
RADIATION HAZARDS
RADIATION PROTECTION
RADIONUCLIDE MIGRATION
REACTOR ACCIDENTS
RISK ASSESSMENT