Numerical simulation of stress properties on high-yield fast-neutron-burst reactor in super-prompt-critical condition
Creators
- 1. Key Laboratory of Neutron Physics, CAEP, Mianyang (China)
- 2. Institute of Nuclear Physics and Chemistry, CAEP, Mianyang (China)
Description
The performance of fast burst reactor (FBR) is mainly restricted by the physical damage caused by the mechanical shock. The smaller burst width and larger fission yield in high-yield FBRs indicate more significant stress variation. To obtain the temporal and spatial distributions of stress/strain of burst in the high-yield FBR and to provide technical support for the design and safety analysis of new-type FBRs, the neutronic calculation based on the point kinetic approximation and Monte Carlo method is first performed to obtain the temporal and spatial distributions of fission power in the cylindrical FBR Godiva IV, the three-dimensional thermoelastic behavior in the burst is then simulated by using the finite element method software ANSYS Mechanical. The dynamic response of stress in material component is obtained and analyzed. The results show that the cylindrical fuel will suffer a stress wave during the burst and the maximum stress occurs in the radial cracking of central fuel rings. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- High Power Laser and Particle Beams
- Journal Volume
- 31
- Journal Issue
- 5
- Journal Page Range
- [6 p.]
- ISSN
- 1001-4322
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 55057829
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; CRACKING; CYLINDRICAL CONFIGURATION; DAMAGE; FAST NEUTRONS; FINITE ELEMENT METHOD; FISSION; FISSION YIELD; FUELS; KINETICS; MONTE CARLO METHOD; NEUTRON TRANSPORT; PULSED REACTORS; SAFETY ANALYSIS; SPATIAL DISTRIBUTION; STRESSES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CHEMICAL REACTIONS; COMPUTER CODES; CONFIGURATION; DECOMPOSITION; DISTRIBUTION; ELEMENTARY PARTICLES; FERMIONS; HADRONS; MATHEMATICAL SOLUTIONS; NEUTRAL-PARTICLE TRANSPORT; NEUTRONS; NUCLEAR REACTION YIELD; NUCLEAR REACTIONS; NUCLEONS; NUMERICAL SOLUTION; PYROLYSIS; RADIATION TRANSPORT; REACTORS; SIMULATION; THERMOCHEMICAL PROCESSES; YIELDS
Optional Information
- Notes
- 8 figs., 2 tabs., 11 refs.; http://dx.doi.org/10.11884/HPLPB201931.180347