Neutron kinetics for system thermal-hydraulic codes
Creators
- 1. Brookhaven National Lab., Upton, NY (United States). Dept. of Advanced Technoloy
Description
For many light water reactor (LWR) calculations, it is necessary to use a multidimensional neutron kinetics model coupled to a thermal-hydraulic model in order to obtain satisfactory results. This need coincides with the fact that in recent years there has been considerable research and development in this field with modelers taking advantage of the increase in computing power that has become available. This progress has now led to coupling the core neutron kinetics and thermal-hydraulics calculation to the nuclear steam supply system thermal-hydraulics. This can now be done with very sophisticated models, and the planning of this coupling and the requisite modeling can take advantage of the experience of many code developers in many countries. This paper us one contribution to the planning process for the next generation of system thermal-hydraulic codes. The paper presents the author', conclusions as to what neutron kinetics model and solution algorithms might be implemented, how to initialize the problem, what thermal-hydraulic boundary conditions are needed by the neutron kinetics, and the modeling for cross sections, power generation, and boron transport. In order to justify recommendations, LWR applications are discussed. 3 refs., 2 tabs
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 11. ENFIR: Meeting on reactor physics and thermal hydraulics
- Imprint Pagination
- 838 p.
- Journal Page Range
- p. 306-311.
Conference
- Title
- Meeting on reactor physics and thermal hydraulics.
- Acronym
- 11. ENFIR
- Dates
- 18-22 Aug 1997.
- Place
- Pocos de Caldas, MG (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 28075510
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; FUEL ASSEMBLIES; FUEL ELEMENTS; FUELS; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; NEUTRONS; NUCLEAR ENGINEERING; NUCLEAR FUELS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR CORES; REACTOR KINETICS; REACTOR PHYSICS; REACTOR TECHNOLOGY; REACTORS; THERMAL ANALYSIS; WWER TYPE REACTORS
- Descriptors DEC
- BARYONS; ELEMENTARY PARTICLES; ENERGY SOURCES; ENGINEERING; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; KINETICS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEONS; POWER REACTORS; RADIATION TRANSPORT; REACTOR MATERIALS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Joint nuclear conference with the 4. ENAN: Brazilian meeting on nuclear applications.