Abstract
The gamma heating evaluation in different materials found in current and future generations of nuclear reactor (EPRTM , 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.
Highlights
Introduction to gamma heating formalismNuclear heating can be shared into a neutron and a photon contribution
Zero power facilities called EOLE and MINERVE dedicated to experimental neutron physics purposes are located at CEA Cadarache
The gamma heating measurements are done with Thermo-Luminescent Detectors (TLD) or Optically Stimulated Luminescent Detectors (OSLD)
Summary
Nuclear heating in power reactor is coming from the energy deposition of charged particles produced by neutron and photon interactions, and the radioactive decay of fission products. 10% of the deposited energy is due to the gamma when it represents almost the entire heating in the reflector (Figure 1).The main source of gamma heating in the core is the fission reaction which represents about 60% (one third from the delayed photons) of the total amount followed by the radiative capture (about 20%) and the inelastic scattering. This distribution may be different from one to another reactor depending on its specific material balance. A compilation of these works is presented in the following parts
Sign-in/Register to view highlights & summary Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
