Published March 2004
| Version v1
Book
Study for benchmark calculation using TORT code in BWR reactor vessel
- 1. Hitachi, Ltd., Power and Industrial Systems Nuclear Systems Division, Hitachi, Ibaraki (Japan)
Description
Sensitivity analyses have been made to improve accuracy of TORT calculations. Reasonable calculation conditions such as number of energy groups, flux convergence criterion, number of angular directions, order to Legendre expansions and the effective densities were investigated. No significant differences are identified from the calculation conditions and neutron energy group structure. It is possible to confirm that the water density of the outer bypass region and the annulus area from the shroud to the RPV is an important parameter for accurate estimation of fast neutrons. (author)
Availability note (English)
Available from the Internet at URL https://www.tandfonline.com/doi/abs/10.1080/00223131.2004.10875655Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the 2nd ITRS international symposium on radiation safety and detection technology (ISORD-2)
- Imprint Pagination
- 545 p.
- Journal Page Range
- p. 101-104
Conference
- Title
- 2. ITRS international symposium on radiation safety and detection technology
- Acronym
- ISORD-2
- Dates
- 24-25 Jul 2003
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51063550
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANGULAR DISTRIBUTION; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CONVERGENCE; EPITHERMAL NEUTRONS; FAST NEUTRONS; GROUP CONSTANTS; MULTIGROUP THEORY; NEUTRON FLUX; REACTOR VESSELS; SENSITIVITY ANALYSIS; SPATIAL DOSE DISTRIBUTIONS; T CODES; THERMAL NEUTRONS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BARYONS; COMPUTER CODES; CONTAINERS; CROSS SECTIONS; DISTRIBUTION; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; NEUTRON TRANSPORT THEORY; NEUTRONS; NUCLEONS; POWER REACTORS; RADIATION DOSE DISTRIBUTIONS; RADIATION FLUX; REACTORS; SIMULATION; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs., 5 figs., 3 tabs.; This record replaces 36063971 Imprint:Published as Supplement 4 (March 2004) of Journal of Nuclear Science and Technology