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Overview of MACCS and MACCS2 development efforts

Description/Abstract

The MELCOR Accident Consequence Code System (MACCS), publicly distributed since 1987, was developed to estimate the potential impacts to the surrounding public of severe accidents at nuclear power plants. The principal phenomena considered in MACCS are atmospheric transport and deposition under time-variant meteorology, short-term and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs of mitigative actions. At this time, no other publicly available code in the US offers all these capabilities. MACCS2 represents a major enhancement of the capabilities of its predecessor MACCS. MACCS2 was developed as a general-purpose analytical tool applicable to diverse reactor and nonreactor Department of Energy (DOE) facilities. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. The new code features allow detailed evaluations of risks to workers at nearby facilities on large DOE reservations and allow the user to assess the potential impacts of over 700 radionuclides that cannot be considered with MACCS.

Creator/Author: Young, M. [Sandia National Labs., Albuquerque, NM (United States). Accident Analysis and Consequence Assessment Dept.] ; Chanin, D. [Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States)]
Publication Date:1996 Aug 01
OSTI Identifier:OSTI ID: 266674; Legacy ID: DE96011843
Report Number(s):SAND--96-1341C; CONF-960912--3
DOE Contract Number:AC04-94AL85000
Other Number(s):Other: ON: DE96011843; TRN: 96:017093
Resource Type:Conference
Resource Relation:Conference: International topical meeting on probabilistic safety assessment - moving toward risk based regulation, Park City, UT (United States), 29 Sep - 3 Oct 1996; Other Information: PBD: [1996]
Research Org:Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Org:USDOE, Washington, DC (United States)
Subject:22 NUCLEAR REACTOR TECHNOLOGY ;21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ;99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; M CODES; EMERGENCY PLANS; RISK ASSESSMENT
Country of Publication:United States
Language:English
Format: Size: 7 p.
Availability: INIS; OSTI as DE96011843
To purchase this media from NTIS, click here
Update Date:2010 Feb 18

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