10 research outputs found
Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors
Etude d'un nouveau capteur à transfert thermique radial mesurant l'énergie induite par interactions rayonnements nucléaires/matière
International audienc
Etude d'un nouveau capteur à transfert thermique radial mesurant l'énergie induite par interactions rayonnements nucléaires/matière
International audienc
Nuclear data production, calculation and measurement: a global overview of the gamma heating issue
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
Nuclear Heating Measurement in Critical Facilities and Experimental Validation of Code and Libraries – An Application to Prompt and Delayed γ Nuclear Data Needs
Study of the Influence of Heat Sources on the Out-of-Pile Calibration Curve of Calorimetric Cells Used for Nuclear Energy Deposition Quantification
International audienceIn the field of nuclear research, the measurement and knowledge of nuclear heating are of crucial importance to carry out accurate studies of the accelerated ageing of materials and the behavior of nuclear fuels under irradiation with precisely imposed temperature conditions. Nuclear heating can be quantified with a differential calorimeter by using in-pile temperature measurements and the preliminary out-of-pile calibration curves of each calorimetric cell. This paper focuses on experimental studies of two new calorimetric cell prototypes developed to test the influence of the Joule effect heating of specific cell body areas on the out-of-pile-calibration curves. The calibration curves are determined, discussed for different applied internal/external thermal conditions, and compared to irradiation data obtained with the CARMEN-1P type calorimeter used in the OSIRIS reflector
Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors
International audienc
Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors
The nuclear heating measurements in Material Testing Reactors (MTRs) are crucial for the study of nuclear materials and fuels under irradiation. The reference measurements of this nuclear heating are especially performed by a differential calorimeter including a graphite sample material. Then these measurements are used for other materials, other geometries, or other experimental conditions in order to predict the nuclear heating and thermal conditions induced in the irradiation devices. This paper will present new simulations with MCNP Monte-Carlo transport code to determine the gamma heating profile inside the calorimeter. The whole complex geometry of the sensor has been considered. We use as an input source in the model, the photon spectra calculated in various positions of CARMEN-1 irradiation program in OSIRIS reactor. After a description of the differential calorimeter device, the MCNP modeling used for the calculations of radial profile of nuclear heating inside the calorimeter elements will be introduced. The obtained results of different simulations will be detailed and discussed in this paper. The charged particle equilibrium inside the calorimeter elements will be studied. Then we will focus on parametric studies of the various components of the calorimeter. The influence of source type will be also took into account. Moreover the influence of the material used for the sample will be described