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Title: Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry Plant

Activities involving regulatory implementation of updated source term information were pursued. These activities include the identification of the source term, the identification of the chemical form of iodine in the source term, and the timing of the source term`s entrance into containment. These activities are intended to support a more realistic source term for licensing nuclear power plants than the current TID-14844 source term and current licensing assumptions. MELCOR calculations were performed to support the technical basis for the updated source term. This report presents the results from three MELCOR calculations of nuclear power plant accident sequences and presents comparisons with Source Term code Package (STCP) calculations for the same sequences. The three low-pressure sequences were analyzed to identify the materials which enter containment (source terms) and are available for release to the environment, and to obtain timing of sequence events. The source terms include fission products and other materials such as those generated by core-concrete interactions. All three calculations, for both MELCOR and STCP, analyzed the Surry plant, a pressurized water reactor (PWR) with a subatmospheric containment design.
Authors:
 [1] ;  [2]
  1. Sandia National Labs., Albuquerque, NM (United States)
  2. Geo-Centers Inc., Albuquerque, NM (United States)
Publication Date:
OSTI Identifier:
142546
Report Number(s):
NUREG/CR--6107; SAND--93-2042
ON: TI94008895; TRN: 94:006603
DOE Contract Number:
AC04-94AL85000
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Mar 1994
Research Org:
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Safety Issue Resolution; Sandia National Labs., Albuquerque, NM (United States); Geo-Centers, Inc., Albuquerque, NM (United States)
Sponsoring Org:
Nuclear Regulatory Commission, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; SURRY-1 REACTOR; LOSS OF COOLANT; COMPUTER CALCULATIONS; M CODES; COMPARATIVE EVALUATIONS; FISSION PRODUCT RELEASE; CONTAINMENT SYSTEMS; BIOSPHERE; SOURCE TERMS; S CODES; AVAILABILITY; REACTOR PROTECTION SYSTEMS; THEORETICAL DATA