Monte Carlo calculations, by means of MCNP code, have been carried out in order to simulate experimental measurementsof 235U content performed at the JRC-Ispra Establishment on MTR fuel elements by means of the "MTR scanner" of the PERLA facility. This paper describes the simulation of both passive and active gamma spectrometry measurements carried out on two different standards of MTR fuel elements. ln particular it deals with the setting up of MCNP code, reporting a comparison between simulated and experimental data of a series of measurements experiencing various diversion strategies of one platelet. Those presented are the first results of a study for the determination, by means of the MCNP code, of a set of parametric corrections, such to reduce the number of standards needed for field measurements.
Monte Carlo simulations of PERLA Gamma Scanner for MTR Fuel Assemblies / Dodaro, A; Frazzoli, F. V.; Guardini, S; Krueger, M; Remetti, Romolo. - STAMPA. - (1995), pp. 737-742.
Monte Carlo simulations of PERLA Gamma Scanner for MTR Fuel Assemblies
REMETTI, Romolo
1995
Abstract
Monte Carlo calculations, by means of MCNP code, have been carried out in order to simulate experimental measurementsof 235U content performed at the JRC-Ispra Establishment on MTR fuel elements by means of the "MTR scanner" of the PERLA facility. This paper describes the simulation of both passive and active gamma spectrometry measurements carried out on two different standards of MTR fuel elements. ln particular it deals with the setting up of MCNP code, reporting a comparison between simulated and experimental data of a series of measurements experiencing various diversion strategies of one platelet. Those presented are the first results of a study for the determination, by means of the MCNP code, of a set of parametric corrections, such to reduce the number of standards needed for field measurements.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
