Prospects for improvement of fuel performance and fuel cycle cost in BWRs and PWRs in the nineties
- 1. Advanced Nuclear Fuels Corp., Richland, WA (USA)
Description
Advanced Nuclear Fuels Corporation (ANF) has developed fuel assembly designs for BWRs and PWRs that can reduce fuel cycle costs by increasing uranium utilization in the reactors. Design features which have been used to increase uranium utilization include natural uranium axial blankets, 9x9 lattices with multiple water rods for BWRs and optimized water to fuel ratio lattices for PWRs. Gadolinia burnable absorber has been used in both BWR and PWR fuel designs to control power peaking which facilitates reactor operation for high burnup and extended cycles. New developments in fuel design and performance will further increase uranium utilization in the nineties. A high performance spacer grid design is being developed by ANF for use in PWRs and BWRs to increase coolant mixing efficiency with a resulting increase in critical heat flux and increased thermal margin which can be used to reduce fuel cycle costs. The development of more corrosion resistant cladding and other fuel design changes should enable fuel to attain assembly burnups of up to 45,000 MWd/MTU for BWRs and 60,000 MWd/MTU for PWRs with two year cycle lengths
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 56
- Journal Issue
- 1
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 485-490
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- 6. Pacific Basin nuclear conference.
- Dates
- 7-11 Sep 1987.
- Place
- Beijing (China).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20064212
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNABLE POISONS; BURNUP; BWR TYPE REACTORS; CRITICAL HEAT FLUX; FORECASTING; FUEL ELEMENTS; FUEL MANAGEMENT; HEAT TRANSFER; LOAD MANAGEMENT; PERFORMANCE; POWER DISTRIBUTION; PWR TYPE REACTORS
- Descriptors DEC
- DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT FLUX; MANAGEMENT; MATERIALS; NEUTRON ABSORBERS; NUCLEAR MATERIALS MANAGEMENT; NUCLEAR POISONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-870905--.