Nuclear data production, calculation and measurement: a global overview of the gamma heating issue

¹ CEA, DEN, DER, SPRC, Cadarache, F-13108 Saint-Paul-lez-Durance, France
² CEA, DEN, DER, SPEx, Cadarache, F-13108 Saint-Paul-lez-Durance, France

Abstract

The gamma heating evaluation in different materials found in current and future generations of nuclear reactor (EPR^TM, GENIV, MTR-JHR), is becoming an important issue especially for the design of many devices (control rod, heavy reflector, in-core & out-core experiments…). This paper deals with the works started since 2009 in the Reactor Studies Department of CEA Cadarache in ordre to answer to several problematic which have been identified as well for nuclear data production and calculation as for experimental measurement methods. The selected subjects are:

• Development of a Monte Carlo code (FIFRELIN) to simulate the prompt fission gamma emission which represents the major part of the gamma heating production inside the core

• Production and qualification of new evaluations of nuclear data especially for radiative capture and inelastic neutron scattering which are the main sources of gamma heating out-core

• Development and qualification of a recommended method for the total gamma heating calculation using the Monte Carlo simulation code TRIPOLI-4

• Development, test and qualification of new devices dedicated to the in-core gamma heating measurement as well in MTR-JHR as in zero power facilities (EOLE-MINERVE) of CEA, Cadarache to increase the experimental measurement accuracy.