Published 1990
| Version v1
Book
Improvement of a three-dimensional transport code and its application to core analysis of large LMFBRs
Creators
- 1. osaka univ., Suita (Japan). Faculty of Engineering
- 2. Power Reactor and Nuclear Fuel Development Corp. Tokyo (Japan)
- 3. Computer Software Development Co. Ltd., Tokyo (Japan)
Description
The three-dimensional transport code TRITAC solves the SN equation in XYZ geometry based on the diffusion synthetic acceleration method. To reduce the computing time of TRITAC particularly for large fast reactors, we have accelerated the diffusion synthetic calculation with SOR, and successed to decrease the computing time to about a factor of 4. We have also improved TRITAC to treat the anisotropic scattering. The spatial mesh effect and the anisotropic scattering effect on key core performance parameters of a large fast critical assembly were investigated using the improved code
Additional details
Publishing Information
- Publisher
- Societe Francaise pour l'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- The physics of reactors: operation, design and computation. Volume 3
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. II.104-II.113.
Conference
- Title
- Operation, Design and Computation.
- Acronym
- International Conference on the Physics of Reactors
- Dates
- 23-27 Apr 1990.
- Place
- Marseille (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 22012727
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTROL ROD WORTHS; LMFBR TYPE REACTORS; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; T CODES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTORS