Deterministic lattice code development at UNIST
Creators
- 1. Department of Nuclear Engineering, Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)
Description
A new method of characteristics code, STREAM, has been developed at Ulsan National Institute of Science and Technology (UNIST). With regard to a resonance treatment in STREAM, the gray resonance treatment method and doubly heterogeneous self-shielding method were implemented based on the equivalence theory. STREAM can calculate eigenvalue and pin power distribution of a two-dimensional multi-assembly with CMFD acceleration. In this paper, designed pin cell and two-dimensional C5G7 benchmark problems were solved to verify the STREAM library and solver, respectively. As a practical problem, the VENUS-2 benchmark from research reactor experiments was calculated up to assembly level by the STREAM code. To check applicability of STREAM to new fuel analysis for a boron free reactor, innovative fuel problems were designed and calculated. STREAM solutions of these problems were compared with the Monte Carlo reference solutions, and showed a good agreement with them on a similar level. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 12 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042780
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION RATIO; FUEL ASSEMBLIES; FUEL PINS; GADOLINIUM; MIXED OXIDE FUELS; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; REACTOR LATTICE PARAMETERS; REACTOR LATTICES; RESONANCE ESCAPE PROBABILITY; S CODES; SELF-SHIELDING; URANIUM 235; URANIUM DIOXIDE; VHTR REACTOR
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; CHALCOGENIDES; COMPUTER CODES; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; EXPERIMENTAL REACTORS; FUEL ELEMENTS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAVY NUCLEI; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FUELS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; RADIOISOTOPES; RARE EARTHS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1106178.pdf; 16 refs., 8 figs., 11 tabs.