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Title: Fuel Element Transfer Cask Modelling Using MCNP Technique

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.
Authors:
;  [1]
  1. Technical Support Division, Malaysian Nuclear Agency (NUCLEAR MALAYSIA), Bangi, 43000 KAJANG (Malaysia)
Publication Date:
OSTI Identifier:
21366878
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1202; Journal 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
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 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