MELCOR Accident Consequence Code System (MACCS)
Creators
- 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
Additional details
Additional titles
- Subtitle (English)
- Volume 1, User's guide
Publishing Information
- Imprint Pagination
- 260 p.
- Report number
- NUREG/CR--4691-Vol.1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21053271
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S54: ENVIRONMENTAL SCIENCES; S54: ENVIRONMENTAL SCIENCES;
- Resource subtype / Literary indicator
- Computer Program Description
- Descriptors DEI
- BIOLOGICAL PATHWAYS; COMPUTER PROGRAM DOCUMENTATION; ENVIRONMENTAL EXPOSURE PATHWAY; ENVIRONMENTAL IMPACTS; HEALTH HAZARDS; M CODES; NUCLEAR POWER PLANTS; RADIATION DOSES; RADIATION TRANSPORT; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; HAZARDS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789
- Notes
- This report contains 3 microfiche supplements.
- Secondary number(s)
- SAND--86-1562-Vol.1.