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Title: Simulation on reactor TRIGA Puspati core kinetics fueled with thorium (Th) based fuel element

In confronting global energy requirement and the search for better technologies, there is a real case for widening the range of potential variations in the design of nuclear power plants. Smaller and simpler reactors are attractive, provided they can meet safety and security standards and non-proliferation issues. On fuel cycle aspect, thorium fuel cycles produce much less plutonium and other radioactive transuranic elements than uranium fuel cycles. Although not fissile itself, Th-232 will absorb slow neutrons to produce uranium-233 ({sup 233}U), which is fissile. By introducing Thorium, the numbers of highly enriched uranium fuel element can be reduced while maintaining the core neutronic performance. This paper describes the core kinetic of a small research reactor core like TRIGA fueled with a Th filled fuel element matrix using a general purpose Monte Carlo N-Particle (MCNP) code.
Authors:
;  [1] ; ; ; ;  [2]
  1. Universiti Tenaga Nasional. Jalan Ikram-UNITEN, 43000 Kajang, Selangor (Malaysia)
  2. Malaysian Nuclear Agency, Bangi, 43000 Kajang, Selangor (Malaysia)
Publication Date:
OSTI Identifier:
22494518
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1704; Journal Issue: 1; Conference: iNuSTEC2015: International muclear science, technology and engineering conference 2015, Negeri Sembilan (Malaysia), 17-19 Aug 2015; Other Information: (c) 2016 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; DESIGN; HIGHLY ENRICHED URANIUM; MONTE CARLO METHOD; NUCLEAR POWER PLANTS; PLUTONIUM; PROLIFERATION; PUSPATI; RESEARCH REACTORS; SAFETY; SECURITY; SLOW NEUTRONS; THORIUM 232; THORIUM CYCLE; TRIGA TYPE REACTORS; URANIUM 233