High flux isotope reactor low-enriched uranium core design optimization studies
Creators
- 1. Oak Ridge National Laboratory, 1 Bethel Valley Rd, Oak Ridge, TN 37830 (United States)
Description
Design optimization studies have been conducted for a High Flux Isotope Reactor low enriched uranium (Leu) core using a high density U-10-Mo monolithic alloy fuel. These studies search a multidimensional design space to provide understanding of the dependence of multiple design objectives on the design choices. Neutronic, isotopic depletion, and thermal hydraulic analyses are incorporated into these studies to generate key performance and safety metrics for assessing the feasibility and fitness of given designs. A design optimization methodology based on response surface methodology has been developed to visualize dependencies and to combine multiple objectives for determining an unbiased overall optimized design. These studies provide an understanding of the effect that design decisions have on the key performance and safety metrics, and establish a basis for further studies to determine truly optimized designs. (Author)
Availability note (English)
Available from the Instituto Nacional de Investigaciones Nucleares, Centro de Informacion y Documentacion, 52750 Ocoyoacac, Estado de Mexico (MX), e-mail: mclaudia.gonzalez@inin.gob.mxAdditional details
Publishing Information
- Publisher
- Sociedad Nuclear Mexicana
- Imprint Place
- Ciudad de Mexico (Mexico)
- Imprint Pagination
- 13 p.
Conference
- Title
- reactor physics paving the way towards more efficient systems
- Acronym
- PHYSOR 2018
- Dates
- 22-26 Apr 2018
- Place
- Cancun, Q. R. (Mexico)
INIS
- Country of Publication
- Mexico
- Country of Input or Organization
- Mexico
- INIS RN
- 49106398
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALLOYS; CALIFORNIUM 252; DENSITY; DESIGN; ENRICHED URANIUM; FUEL PLATES; HFIR REACTOR; METRICS; NUCLEAR FUELS; OPTIMIZATION; PERFORMANCE; SAFETY; THERMAL HYDRAULICS; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; CALIFORNIUM ISOTOPES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; FLUID MECHANICS; FUEL ELEMENTS; FUELS; HEAVY NUCLEI; HYDRAULICS; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; ISOTOPES; MATERIALS; MECHANICS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; PHYSICAL PROPERTIES; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; URANIUM; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES