Methodology of RTP fuel management using TRIGAM code
Creators
- 1. Malaysian Inst. for Nuclear Technology Research MINT, Bangi (Malaysia). Special Projects Div.
Description
The paper describes a methodology that have been used for fuel elements burn-up calculations and in-core fuel management. A TRIGAM code has been developed by a group of researcher from JSI, Yugoslavia. It was developed for reactor physics calculations of TRIGA PUSPATI Reactor (RTP). A TRIGAM code contains the main programme, TRIGAP and database of effective group constants and fuel elements data. It is divided into three subroutines: SIGMA, CEBIS and BURN. SIGMA calculates the ring-smeared two-group diffusion constants using the effective 2 group cross-sections for all types of unit cells that are stored in the database as a function of burn-up. CEBIS is an independent one-dimensional two-group diffusion code. With ring averaged power distributions from CEBIS, corresponding power, xenon and samarium corrections can be calculated. On the basis of total energy produced by the reactor and core power distributions, subroutine BURN calculates the burn up of each elements in current step. (Author)
Availability note (English)
Available at Malaysian Inst. for Nuclear Technology Research (MINT), Bangi, Malaysia; Ainon@mint.gov.myAdditional details
Publishing Information
- Publisher
- Malaysian Inst. for Nuclear Technology Research MINT
- Imprint Place
- Bangi (Malaysia)
- Imprint Pagination
- 6 p.
Conference
- Title
- 2003 MINT Technical Convention
- Dates
- 22-24 Jul 2003
- Place
- Bandar Baru Bangi (Malaysia)
INIS
- Country of Publication
- Malaysia
- Country of Input or Organization
- Malaysia
- INIS RN
- 36088634
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; FUEL ELEMENTS; FUEL MANAGEMENT; GROUP CONSTANTS; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; ONE-DIMENSIONAL CALCULATIONS; POWER DENSITY; POWER DISTRIBUTION; REACTOR CORES; RTP REACTOR; SAMARIUM OSCILLATIONS; T CODES; XENON OSCILLATIONS
- Descriptors DEC
- COMPUTER CODES; CROSS SECTIONS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MANAGEMENT; NEUTRON TRANSPORT THEORY; NUCLEAR MATERIALS MANAGEMENT; PARTIAL DIFFERENTIAL EQUATIONS; POISONING; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; TRANSPORT THEORY; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS