Published February 1990 | Version v1
Report Restricted

MELCOR Accident Consequence Code System (MACCS)

  • 1. Technadyne Engineering Consultants, Inc., Albuquerque, NM (USA)
  • 2. Sandia National Labs., Albuquerque, NM (USA)

Description

This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previous CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projection, dose accumulation by a number of pathways including food and water ingestion, early and latent health effects, and economic costs. The MACCS code can be used for a variety of applications. These include (1) probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, (2) sensitivity studies to gain a better understanding of the parameters important to PRA, and (3) cost-benefit analysis. This report is composed of three volumes. This document, Volume 1, the Users's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems

Availability note (English)

MF available from INIS under the Report Number; NTIS, PC E10/MF E01 - GPO as TI90009797; OSTI; INIS.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Subtitle (English)
Volume 1, User's guide

Publishing Information

Imprint Pagination
260 p.
Report number
NUREG/CR--4691-Vol.1

Optional Information

Contract/Grant/Project number
Contract AC04-76DP00789
Notes
This report contains 3 microfiche supplements.
Secondary number(s)
SAND--86-1562-Vol.1.