Abstract. The paper presents calculation results for experiments performed to address needs of the MOX fuel manufacturing process and particularly with low-moderated MOX fissile media. Computation of criticality for eleven configurations and reaction rates ratios for major and minor actinides are performed with CRISTAL french criticality code package, and the reference MCNPX and TRIPOLI-4.3 codes. The multigroup JEF-2.2, JEFF-3.1 and continuous energy JEF-2.2, JEFF-3.1, ENDF/B-VI and ENDF/B-VII neutron cross sections are used for the computations. The results are compared to verify group-wise calculations. Then the obtained calculated values will be used to predict eigenvalue accuracy for applications with damp MOX powder, and to validate 238 U, 239 Pu, and 240 Pu cross sections.
In the event of a criticality accident, not only the maximal doses received by the victims must be determined but it is also crucial to evaluate the doses to the different organs. With a neutron component, morphology is a key parameter in the organ dose calculation. As the simulation tools can be time consuming to proceed, especially if morphology is taken into account, for all the victims, it may be very useful to have a database of conversion coefficients that allow to obtain the organ doses from the dose measured in the dosemeter for different kinds of morphology. In this paper, we present a study performed to evaluate such conversion coefficients using voxelized anthropomorphic phantoms. These coefficients take into account two crucial parameters having an impact on the dose at the organs: the orientation of the victim in the radiation field and the morphology, that is to say the body mass index of the different victims.
Abstract. In the framework of criticality safety, the validation of the APOLLO2-MORET 4 calculation route, performed by IRSN, is based on the calculation of more than 1800 integral experiments. Calculations were performed on this huge validation database using group-wise nuclear data libraries based on JEFF-3.1 evaluation files. Calculation-experiment discrepancies were analyzed regarding the neutron spectrum. This validation highlights that the JEFF-3.1 evaluation gives markedly better results than those obtained with the JEF-2.2 evaluated library for many of the criticality applications.
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