Neutronic simulation of a research reactor core of (232Th, 235U)O 2 fuel using MCNPX2.6 code

Feghhi, S.A.H.; Rezazadeh, Marzieh; Kadi, Y.; Tenreiro, Claudio; Aref, Morteza; Gholamzadeh, Zohreh

doi:10.1007/s12043-012-0462-7

Cited by 1 publication

(1 citation statement)

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“…The result from the simulation will be compared with other similar study of Th-232 fuel applied to pool type research reactor [2], where parametric study of a research reactor with hexagonal 19 assembly core containing 232 Th and 235 U with 2.2% enrichment fuel simulation were carried out. A maximum K eff of 1.00026 was achieved for a critical core configuration.…”

Section: Methodsmentioning

confidence: 99%

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

Mohammed

Pauzi²,

Rahman

et al. 2016

AIP Conference Proceedings

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Abstract.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 ( 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.

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Section: Methodsmentioning

confidence: 99%