This work is focused on the validation of the MCB code and its application to burn-up calculation and core optimization of the Pavia TRIGA Mark II research nuclear reactor installed at the Laboratory of Applied Nuclear Energy (LENA- University of Pavia). The validation has been performed with two different methods. The first one consists of a comparison between the code outputs and the values of the induced activity measured for some nuclides produced by neutron irradiation of natural uranium and thorium foils in the reactor experimental channels. The second one is based of the comparison of the code outputs and the results obtained solving a system of differential equations (Bateman equations) which describes the time evolution of the actinides and fission products. The experimental and analytical results have been compared with the data obtained from simulations resulting in a good agreement. The validation of the MCB code allowed the optimization of the Pavia TRIGA reactor core.

Study of core optimization of the Pavia TRIGA reactor using MCB code and experimental measurements

ALLONI, DANIELE;BORIO DI TIGLIOLE, ANDREA;PANZA, FABIO;PRATA, MICHELE
In corso di stampa

Abstract

This work is focused on the validation of the MCB code and its application to burn-up calculation and core optimization of the Pavia TRIGA Mark II research nuclear reactor installed at the Laboratory of Applied Nuclear Energy (LENA- University of Pavia). The validation has been performed with two different methods. The first one consists of a comparison between the code outputs and the values of the induced activity measured for some nuclides produced by neutron irradiation of natural uranium and thorium foils in the reactor experimental channels. The second one is based of the comparison of the code outputs and the results obtained solving a system of differential equations (Bateman equations) which describes the time evolution of the actinides and fission products. The experimental and analytical results have been compared with the data obtained from simulations resulting in a good agreement. The validation of the MCB code allowed the optimization of the Pavia TRIGA reactor core.
In corso di stampa
Nuclear Engineering covers resources concerned with the branch of engineering that deals with the production and use of nuclear energy, including the development, design, construction, and operation of power plants that convert energy produced by fission or fusion to other useful forms of energy such as heat and light.
Esperti non anonimi
Inglese
Internazionale
STAMPA
nuclear reactor, TRIGA Mark II, burn up, Monte Carlo Simulations, MCNP, MCB, gamma spectrometry
no
5
info:eu-repo/semantics/article
262
Alloni, Daniele; BORIO DI TIGLIOLE, Andrea; Bruni, J.; Panza, Fabio; Prata, Michele
1 Contributo su Rivista::1.1 Articolo in rivista
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11571/1167285
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