Preliminary design on core physics of medium-size modular lead-cooled fast reactor M2LFR-1000
- 1. University of Science and Technology of China, Hefei (China)
Description
[Background] The Lead-cooled fast reactor (LFR) features high operation temperature, low-pressure and chemically inert liquid lead with good thermodynamic properties as coolant, hence it has an irreplaceable advantage in production of electricity and consuming actinides from spent pressurized water reactor (PWR) fuel. [Purpose] This study aims to explore preliminary design on core physics of the 1000 MW (thermo) medium-size modular lead-cooled fast reactor (M2LFR-1000) proposed by University of Science and Technology of China (USTC). [Methods] After obtaining the atom density of the nuclides at different burn-up levels by using SRAC/COREBN code, the Monte Carlo code MCNP (Monte Carlo N Particle Transport Code) was employed to conduct the preliminary neutronic design of the core and burn-up analysis. [Results] The results of calculations cover the core power distribution, reactivity coefficient, neutron kinetic parameters, control rod worth and core lifetime. Especially, the capability of M2LFR-1000 core to transmute minor actinides was evaluated. [Conclusions] Results show that the M2LFR-1000 core scheme is reasonable, satisfies the design requirements and has excellent capability to transmute Minor Actinides. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Techniques
- Journal Volume
- 41
- Journal Issue
- 10
- Journal Page Range
- p. 88-94
- ISSN
- 0253-3219
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 54104986
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACTINIDES; BURNUP; CONTROL ROD WORTHS; DESIGN; LEAD COOLED REACTORS; LIQUIDS; MONTE CARLO METHOD; NEUTRON TRANSPORT; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTOR KINETICS; THERMODYNAMICS
- Descriptors DEC
- CALCULATION METHODS; ELEMENTS; ENRICHED URANIUM REACTORS; FLUIDS; KINETICS; LIQUID METAL COOLED REACTORS; METALS; NEUTRAL-PARTICLE TRANSPORT; POWER REACTORS; RADIATION TRANSPORT; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 figs., 6 tabs., 23 refs.; http://dx.doi.org/10.11889/j.0253-3219.2018.hjs.41.100606