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The MUSE-4 experiment : Prompt reactivity and delayed neutron measurements

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  • [Phys:Nexp] Physics/Nuclear Experiment
  • [Phys:Nexp] Physique/Physique Nucléaire Expérimentale


The MUSE-4 Experiment: Prompt Reactivity and Delayed Neutron Measurements A.Billebaud, J.Vollaire, R.Brissot, D.Heuer, C.Le Brun, E.Liatard, J.-M.Loiseaux, O.Me´plan, E.Merle-Lucotte, and F.Perdu. Laboratoire de Physique Subatomique et de Cosmologie, IN2P3-CNRS/UJF, 53, av. des Martyrs, F-38026 Grenoble Cedex, France [email protected] C.Destouches, P.Chaussonnet, and J.-M.Laurens. CEA Cadarache, DEN/DER/SPEx/LPE, F-13108 Saint-Paul-lez-Durance Cedex, France ABSTRACT - The use of systems such as Accelerator Driven Systems (ADSs) for incineration of nuclear waste and/or energy production will require monitoring of different parameters which govern the reactor safety. The MUSE-4 experiment performed at CEA Cadarache Centre (France) in the MASURCA reactor coupled to the GENEPI accelerator allows the study of new techniques to perform this monitoring in subcritical medium. We detail two experimental methods to determine the prompt multiplication factor kp and the delayed neutron fraction βeff . kp values are obtained from time responses of the core measured with fission chambers after a neutron pulse. We propose a new approach based on the distribution of time intervals between two consecutive events in a fission chain obtained from a MCNP simulation. From the decrease rates of time spectra simulated for different subcriticality levels compared to experimental rates, the determination of the prompt multiplication factor is done. The delayed neutron fraction is obtained by varying suddenly the GENEPI source intensity. The response of a neutron detector immediately before and after the source change allows the determination of the ratio ρ βeff between the reactivity and the fraction of the delayed neutrons. We show that these two methods applied for two reactivity levels give finally βeff and keff which are found in excellent agreement with expected values. I. INTRODUCTION One of the most important problem with nuclear energy is the management of the large amount of plutonium and mi- no

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