skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: MELCOR computer code manuals

Abstract

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, whichmore » describe the phenomenological models that have been implemented in each package.« less

Authors:
; ; ; ;  [1]; ; ;  [2]
  1. Sandia National Labs., Albuquerque, NM (United States)
  2. Oak Ridge National Lab., TN (United States)
Publication Date:
Research Org.:
Sandia National Labs., Albuquerque, NM (United States); Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
50939
Report Number(s):
NUREG/CR-6119-Vol.2; SAND-93-2185-Vol.2
ON: TI95010660; TRN: 95:011918
DOE Contract Number:  
AC04-94AL85000
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Mar 1995
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; M CODES; MANUALS; REACTOR CORE DISRUPTION; WATER COOLED REACTORS; US NRC; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; FISSION PRODUCT RELEASE; PRIMARY COOLANT CIRCUITS; CONTAINMENT BUILDINGS; ENGINEERED SAFETY SYSTEMS; HYDROGEN PRODUCTION

Citation Formats

Summers, R.M., Cole, R.K. Jr., Smith, R.C., Stuart, D.S., Thompson, S.L., Hodge, S.A., Hyman, C.R., and Sanders, R.L. MELCOR computer code manuals. United States: N. p., 1995. Web. doi:10.2172/50939.
Summers, R.M., Cole, R.K. Jr., Smith, R.C., Stuart, D.S., Thompson, S.L., Hodge, S.A., Hyman, C.R., & Sanders, R.L. MELCOR computer code manuals. United States. doi:10.2172/50939.
Summers, R.M., Cole, R.K. Jr., Smith, R.C., Stuart, D.S., Thompson, S.L., Hodge, S.A., Hyman, C.R., and Sanders, R.L. Wed . "MELCOR computer code manuals". United States. doi:10.2172/50939. https://www.osti.gov/servlets/purl/50939.
@article{osti_50939,
title = {MELCOR computer code manuals},
author = {Summers, R.M. and Cole, R.K. Jr. and Smith, R.C. and Stuart, D.S. and Thompson, S.L. and Hodge, S.A. and Hyman, C.R. and Sanders, R.L.},
abstractNote = {MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package.},
doi = {10.2172/50939},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {3}
}