Measurements flux i four positions of a radial piercing channel of TRIGA Mark II nuclear reactor of Pavia was performed by means of a bare irradiation method and a Monte Carlo simulation both relying on Ni monitors. Reaction rates per target nucleus of Ni, obtained from measurement and simulation, were compared in order to verify the accuracy of the simulations. A satisfactory agreement was observed since the results were compatible within the stated uncertainties with exception of values related to the position closest to the reactor core, where a discrepancy at ten percent level was highlighted. Consequently, the Monte Carlo code used for the simulation was considered to be validated and thus, intended to be used in the forthcoming structural modifications of the channel D which include neutron shielding and thermal neutron filter.

Conventional fast neutron flux measurement in the radial piercing channel D of the TRIGA Mark II Reactor, Pavia

S. Fatemi
Membro del Collaboration Group
;
B. Smilgys
Membro del Collaboration Group
;
A. Salvini
Membro del Collaboration Group
;
M. Oddone
Membro del Collaboration Group
;
S. Altieri
Membro del Collaboration Group
;
M. Prata
Membro del Collaboration Group
2021

Abstract

Measurements flux i four positions of a radial piercing channel of TRIGA Mark II nuclear reactor of Pavia was performed by means of a bare irradiation method and a Monte Carlo simulation both relying on Ni monitors. Reaction rates per target nucleus of Ni, obtained from measurement and simulation, were compared in order to verify the accuracy of the simulations. A satisfactory agreement was observed since the results were compatible within the stated uncertainties with exception of values related to the position closest to the reactor core, where a discrepancy at ten percent level was highlighted. Consequently, the Monte Carlo code used for the simulation was considered to be validated and thus, intended to be used in the forthcoming structural modifications of the channel D which include neutron shielding and thermal neutron filter.
978-961-6207-49-2
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/11571/1430454
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