Summary of MELCOR 1.8.2 calculations for three LOCA sequences (AG, S2D, and S3D) at the Surry Plant
Creators
- 1. Sandia National Labs., Albuquerque, NM (United States)
- 2. Geo-Centers Inc., Albuquerque, NM (United States)
Description
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
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as TI94008895; NTIS; GPO.Files
25047655.pdf
Files
(6.6 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 186 p.
- Report number
- NUREG/CR--6107
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25047655
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- AVAILABILITY; BIOSPHERE; COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; CONTAINMENT SYSTEMS; FISSION PRODUCT RELEASE; LOSS OF COOLANT; M CODES; REACTOR PROTECTION SYSTEMS; S CODES; SOURCE TERMS; SURRY-1 REACTOR; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINMENT; DATA; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-94AL85000
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- SAND--93-2042.