Sodium void reactivity worth calculations for fast critical assemblies without whole-lattice homogenization
Creators
- 1. Japan Atomic Energy Agency, Oarai, Ibaraki, (Japan)
- 2. Hokkaido Univ., Sapporo, Hokkaido (Japan)
Description
In the present paper, we calculate the sodium void reactivity worth of fast critical assemblies without whole-lattice homogenization in order to reduce errors associated with lattice homogenization. Firstly, we solve a neutron transport benchmark problem simulating fast critical assemblies composed of thin material plates with a discrete ordinates transport solver. The discrete ordinates transport solutions agree well with the Monte Carlo reference solutions; hence, we confirm the validity of the deterministic transport calculations for the sodium void reactivity worth of lattice-heterogeneous critical assemblies. Thereafter, the existing experimental data are calculated without whole-lattice homogenization. The result suggests that the lattice homogenization results in the overestimation of the leakage component of sodium void reactivity worth when the leakage component parallel to plate boundaries is dominant. Utilizing the numerical method without whole-lattice homogenization and the nuclear data JENDL-3.3, numerical solutions agree with the experimental data within 3σ of the experimental uncertainties. (author)
Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 44
- Journal Issue
- 12
- Journal Page Range
- p. 1526-1534
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53076986
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; DISCRETE ORDINATE METHOD; M CODES; NEUTRON TRANSPORT; NUMERICAL SOLUTION; REACTIVITY WORTHS; SODIUM; VOIDS; ZEBRA REACTOR; ZPR-9 REACTOR
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; CALCULATION METHODS; COMPUTER CODES; ELEMENTS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; MATHEMATICAL SOLUTIONS; METALS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; ZERO POWER REACTORS
Optional Information
- Notes
- 11 refs., 9 figs., 12 tabs.; This record replaces 39055144