Fuel Element Transfer Cask Modelling Using MCNP Technique
- Technical Support Division, Malaysian Nuclear Agency (NUCLEAR MALAYSIA), Bangi, 43000 KAJANG (Malaysia)
After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement.
- OSTI ID:
- 21366878
- Journal Information:
- AIP Conference Proceedings, Vol. 1202, Issue 1; Conference: International conference on neutron and X-ray scattering - 2009, Kuala Lumpur (Malaysia), 29 Jun - 1 Jul 2009; Other Information: DOI: 10.1063/1.3295593; (c) 2009 American Institute of Physics; ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
FUEL ELEMENTS
MONTE CARLO METHOD
REACTOR FUELING
RECOMMENDATIONS
SHIELDING
SIMULATION
SPENT FUELS
TRIGA TYPE REACTORS
CALCULATION METHODS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
MATERIALS
NUCLEAR FUELS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS