Core physics calculation study of miniature lead-bismuth cooled nuclear reactor
Description
Aiming at the application environment of small marine nuclear power platform, a 1MW Lead-Bismuth cooled nuclear reactor design scheme was proposed. The Monte Carlo method was used to calculate the reactor core physical parameters. 469 core fuel rods were arranged in 13 turns and 90% enriched UO2 fuel loading meet the power operation of nearly 10 years, and the core size meets the environmental requirements. The calculation results of fuel consumption show that after each loading, the reactor can run continuously for 1 year at 1 MW power. The radial density and axial flux density distribution and power distribution gradient trend of the core are reasonable, indicating that the design scheme can meet the requirements of small ships. Nuclear power platform use requirements. (paper)
Availability note (English)
Available from http://dx.doi.org/10.1088/1755-1315/354/1/012028Additional details
Identifiers
Publishing Information
- Journal Title
- IOP Conference Series: Earth and Environmental Science (Online)
- Journal Volume
- 354
- Journal Issue
- 1
- Journal Page Range
- [7 p.]
- ISSN
- 1755-1315
Conference
- Title
- International Conference on New Energy and Future Energy System
- Dates
- 21-24 Jul 2019
- Place
- Macao (China)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53070124
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BISMUTH; DENSITY; FLUX DENSITY; FUEL CONSUMPTION; FUEL RODS; LEAD; MONTE CARLO METHOD; NUCLEAR POWER; POWER DISTRIBUTION; REACTOR CORES; REACTOR DESIGN; REACTORS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; DESIGN; ELEMENTS; ENERGY CONSUMPTION; FUEL ELEMENTS; METALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER; REACTOR COMPONENTS; REACTOR LIFE CYCLE; URANIUM COMPOUNDS; URANIUM OXIDES