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Title: The Use of MACCS in a Non-Reactor Application

Conference ·
OSTI ID:9735

Dose calculations were performed using the MELCOR Accident Consequence Code System (MACCS) to support safety analyses for the Los Alamos Neutron Science Center (LANSCE) facility. The LANSCE facility is operated and maintained at Los Alamos National Laboratory (LANL) and will be used to conduct experiments for the U.S. Department of Energy (DOE) to investigate the use of accelerators to produce tritium. This paper focuses on tbe methodology adopted in tbe evaluation of doses from potential accidental releases of radioactive material from the LANSCE facility. Some results of the dose calculations are presented. Also discussed are the important features of an isotope screening process developed for this application to limit the number of consequence calculations.

Research Organization:
Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC04-94AL85000
OSTI ID:
9735
Report Number(s):
SAND99-1982C; ON: DE00009735
Resource Relation:
Conference: International MACCS Users Group Meeting; Upton, NY; 11/04-05/1998
Country of Publication:
United States
Language:
English