STP1550

    Development and Experimental Validatio of a Calculation Scheme for Nuclear Heating Evaluation in the Core of the OSIRIS Material Testing Reactor

    Published: Aug 2012


      Format Pages Price  
    PDF (1.7M) 14 $25   ADD TO CART
    Complete Source PDF (53M) 14 $174   ADD TO CART


    Abstract

    The control of the temperature in material samples irradiated in a material testing reactor requires the knowledge of the nuclear heating caused by the energy deposition by neutrons and photons interacting in the irradiation device structures. Thus, a neutron–photonic three-dimensional calculation scheme has been developed to evaluate the nuclear heating in experimental devices irradiated in the core of the OSIRIS MTR reactor (CEA/Saclay Center). The aim is to obtain a predictive tool for the nuclear heating estimation in irradiation devices. This calculation scheme is mainly based on the TRIPOLI-4 three-dimensional continuous-energy Monte Carlo transport code, developed by CEA (Saclay Center). An experimental validation has been carried out on the basis of nuclear heating measurements performed in the OSIRIS core. After an overview of the experimental devices irradiated in the OSIRIS reactor, we present the calculation scheme and the first results of the experimental validation.

    Keywords:

    nuclear heating, OSIRIS reactor, TRIPOLI-4 Monte Carlo code


    Author Information:

    Malouch, F.
    Engineer-Researcher in Nuclear Reactor Physics, Alternative Energies and Atomic Energy Commission (CEA),


    Paper ID: STP155020120033

    Committee/Subcommittee: E10.07

    DOI: 10.1520/STP155020120033


    CrossRef ASTM International is a member of CrossRef.