One-dimensional kinetics modifications for BWR reload methods
Creators
Description
Yankee Atomic Electric Company (YAEC) currently uses RETRAN-02 to analyze limiting transients and establish operating minimum critical power ratio (MCPR) limits for Vermont Yankee (VY) boiling water reactor (BWR) reload analysis. The US Nuclear Regulatory Commission-approved analysis methods, used in previous cycles, use the point-kinetics modeling option in RETRAN-02 to represent transient-induced neutronic feedback. RETRAN-02 also contains a one-dimensional (1-D) kinetics neutronic feedback model option that provides a more accurate transient power prediction than the point-kinetics model. In the past few fuel cycles, the thermal or MCPR operating margin at VY has eroded due to increases in fuel cycle length. To offset this decrease, YAEC has developed the capability to use the more accurate 1-D kinetics RETRAN option. This paper reviews the qualification effort for the YAEC BWR methods. This paper also presents a comparison between RETRAN-02 predictions using 1-D and point kinetics for the limiting transient, and demonstrates the typical gain in thermal margin from 1-D kinetics
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 352-353.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-16 Nov 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038774
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; FUEL MANAGEMENT; HEAT TRANSFER; HYDRAULICS; ONE-DIMENSIONAL CALCULATIONS; OPTIMIZATION; PRESSURIZATION; PRIMARY COOLANT CIRCUITS; R CODES; REACTIVITY; REACTOR CORES; REACTOR KINETICS; REACTOR OPERATION; REACTOR SAFETY; REACTOR START-UP; SCRAM; SENSITIVITY ANALYSIS; TRANSIENTS; US NRC; VERMONT YANKEE REACTOR
- Descriptors DEC
- BWR TYPE REACTORS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; KINETICS; MANAGEMENT; NATIONAL ORGANIZATIONS; NUCLEAR MATERIALS MANAGEMENT; OPERATION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SIMULATION; START-UP; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.