Out-of-core fuel management optimization utilizing the integer linear programming technique
Description
Nuclear fuel management decisions for light water reactors can be categorized as out-of-core and in-core decisions. Out-of-core decisions concern what fuel and burnable absorbers to place in the core and in-core decisions concern where to place them. This paper reports on an automated capability to determine the optimum values of out-of-core fuel management decisions. The objective is to determine the optimum cycling scheme so that the levelized fuel cycle cost over a planning horizon is minimized without violating any constraints. The cycle energy requirements are assumed known. By discharging the least reactive fuel at the end of each cycle, the burned assemblies to reinsert are determined. Selecting the number of fresh assemblies as the decision variables, the enrichments of these assemblies are uniquely specified by the cycle energy requirements. Constraints considered include maximum enrichment and discharge burnup limits. In addition, to assure quarter-core symmetry, the number of fresh assemblies is constrained to multiples of four
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 50
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 95-96
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society winter meeting.
- Dates
- 10-15 Nov 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17083191
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPUTER CODES; F CODES; FUEL CYCLE; FUEL MANAGEMENT; NEUTRON ABSORBERS; NUCLEAR FUELS; PLANNING; PWR TYPE REACTORS; REACTOR KINETICS; SLIGHTLY ENRICHED URANIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; FUELS; ISOTOPE ENRICHED MATERIALS; KINETICS; MANAGEMENT; MATERIALS; METALS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-851115--.