Model development for plant Vogtle utilizing ALPHA/PHOENIX-P/ANC methodology
Creators
Description
The Westinghouse advanced in-core fuel management system (ALPHA/PHOENIX-P/ANC) has been utilized to generate models and predict start-up physics test parameters for the Vogtle units. The initial cores for each unit had an out-in loading pattern and used standard burnable absorbers. In cycle 2 of each unit, low-leakage loading patterns and wet annular burnable absorbers (WABAs) were implemented. Plans call for VANTAGE-5 fuel and integral fuel burnable absorbers (IFBAs) to be implemented in Vogtle 1 cycle 4 and Vogtle 2 cycle 3. Start-up results are discussed for the cycles for which start-up results and final models are now available. Southern Company Services (SCS) is using the Westinghouse code system because the methodology was licensed by the US Nuclear Regulatory Commission, and because of the user support supplied by Westinghouse. The Vogtle ALPHA/PHOENIX-P/ANC models were developed by SCS with Westinghouse oversight as part of a technology transfer agreement
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 502-504.
- 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
- 24038883
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; BURNABLE POISONS; FUEL MANAGEMENT; IMPLEMENTATION; MULTIGROUP THEORY; NEUTRON FLUX; P CODES; REACTOR CORES; REACTOR PHYSICS; REACTOR START-UP; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; US NRC; VOGTLE-1 REACTOR; VOGTLE-2 REACTOR
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; MANAGEMENT; MATERIALS; NATIONAL ORGANIZATIONS; NEUTRON ABSORBERS; NUCLEAR MATERIALS MANAGEMENT; NUCLEAR POISONS; POWER REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; START-UP; THERMAL REACTORS; TRANSPORT THEORY; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.