Publications (9)2.89 Total impact
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Article: Application of the Modified Source Multiplication (MSM) Technique to Subcritical Reactivity Worth Measurements in Thermal and Fast Reactor Systems
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ABSTRACT: The Amplified Source Multiplication (ASM) method and its improved Modified Source Multiplication (MSM) method have been widely used in the CEA's EOLE and MASURCA critical facilities over the past decades for the determination of reactivity worths by using fission chambers in subcritical configurations. The ASM methodology uses relatively simple relationships between count rates of efficient miniature fission chambers located in slightly subcritical reference and perturbed configurations. While this method works quite well for small reactivity variations, the raw results need to be corrected to take into account the flux perturbation at the fission chamber location. This is performed by applying to the measurement a correction factor called MSM. This paper describes in detail both methodologies, with their associated uncertainties. Applications on absorber cluster worth in the MISTRAL-4 full MOX mock-up core and the last core loaded in MASURCA show the importance of the MSM correction on raw ASM data.IEEE Transactions on Nuclear Science 07/2011; · 1.45 Impact Factor -
Article: Neutron Commissioning in the New CABRI Water Loop Facility
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ABSTRACT: The CABRI experimental reactor is located at the Cadarache nuclear research center, southern France. It is operated by the Atomic Energy Commission (CEA) and devoted to Institut de Radioprotection et de Sûreté Nucléaire (IRSN) safety programs. It has been successfully operated during the last 30 years, enlightening the knowledge of FBR and LWR fuel behavior during Reactivity Insertion Accident (RIA) and Loss Of Coolant Accident (LOCA) transients in the frame of Institut de Protection et de Sûreté Nucléaire (IPSN) and now IRSN programs devoted to reactor safety. This operation was interrupted in 2003 to allow for a whole facility renewal program. The main goal of this reconstruction project is to meet thermal hydraulics parameters identical to LWR standard and downgraded conditions, in particular for the need of the CABRI International Programme (CIP) carried out by IRSN under the OECD umbrella. For this, the sodium cooled experimental loop is now being replaced by a pressurized water loop. The distinctive features of CABRI core allow for a specific neutron commissioning program. This paper presents the parameters to be measured with associated experimental methods and also briefly introduces the instrumentation set up.IEEE Transactions on Nuclear Science 11/2010; · 1.45 Impact Factor -
Conference Proceeding: Application of the Modified Source Multiplication (MSM) technique to subcritical reactivity worth measurements in thermal and fast reactor systems
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ABSTRACT: The Amplified Source Multiplication (ASM) method and its improved Modified Source Multiplication (MSM) method have been widely used in the CEA's EOLE and MASURCA critical facilities over the past decades for the determination of reactivity worths by using fission chambers in subcritical configurations. They have been successfully applied to absorber (single or clusters) worth measurement in both thermal and fast spectra, or for (sodium or water) void reactivity worths. The ASM methodology, which is the basic technique to estimate a reactivity worth, uses relatively simple relationships between count rates of efficient miniature fission chambers located in slightly subcritical reference and perturbed configurations. If this method works quite well for small reactivity variation (a few effective delayed neutron fraction), its raw results needs to be corrected to take into account the flux perturbation in the fission chamber. This is performed by applying to the measurement a correction factor called MSM. Its characteristics is to take into account the local space and energy variation of the spectrum in the fission chamber, through standard perturbation theory applied to neutron transport calculation in the perturbed configuration. The proposed paper describes in details both methodologies, with their associated uncertainties. Applications on absorber cluster worth in the MISTRAL-4 full MOX mock-up core and the last core loaded in MASURCA show the importance of the MSM correction on raw data.Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on; 07/2009 -
Article: Neutronic studies in support of accelerator-driven systems: The MUSE experiments in the MASURCA facility
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ABSTRACT: The MUSE program (multiplication with an external source) is in progress at the MASURCA critical facility at the Cadarache Research Center of the Commissariat à l'Energie Atomique in France. The program is dedicated to the physics studies of accelerator-driven systems in support of transmutation studies of minor actinides and long-lived fission products. It began in 1995 with the coupling of a Cf source in MASURCA and was followed by a commercial (d,T) source. In 2001, a specially constructed (d,D)/(d,T) neutron generator (GENEPI) was placed in MASURCA and the MUSE-4 program commenced. We describe the first phases of the MUSE-4 program, with data presented that were obtained up to about the summer of 2002. We present some results from the "reference" configuration, which can operate at critical. We present traverses of measured fission reaction rates, with comparison to calculations. Also in the reference configuration, we performed activation foil measurements and present these results compared to calculations. Because a major objective of the MUSE program is to test and qualify methods of subcritical reactivity measurement, we have devoted a major portion of our studies to this area. We have used classical methods (rod drop, source multiplication) to attempt to measure the subcritical level. In these early phases we studied core configurations of around k_eff = 0.995. Deeper subcriticality (k_eff = 0.96) was achieved by inserting a safety rod. In addition to the methods mentioned above, we have devoted a lot of effort to pulse neutron source, fluctuation (Rossi-alpha and Feynman-alpha), and transfer function methods (e.g., cross-power spectral density). We present our preliminary results of all the methods, with some discussion regarding cross comparison. -
Article: The GENEPI accelerator operation feedback at the MASURCA reactor facility
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ABSTRACT: The MUSE-4 experiment, dedicated to the Accelerator Driven System (ADS) development studies, was achieved in the MASURCA nuclear reactor facility from 2000 to 2004. An external neutron source was introduced in a lead buffer zone located at the centre of the reactor core in order to simulate the spallation source. This paper deals with the GENEPI accelerator operation feedback at the MASURCA reactor facility during the MUSE-4 experimental campaign. After a presentation of the MASURCA mock-up facility and of the experimental programme objectives, the different phases of the accelerator design and realization are detailed. Its installation in the MASURCA nuclear facility, achieved in June 2000, is described concerning the technical and administrative topics. Then, the accelerator operation feedback is given concerning maintenance, tritium target management, source monitoring, technical evolutions, etc. The accelerator partial dismantling, achieved in the first part of 2005, is also presented. In addition, the GENEPI contribution to the MUSE-4 programme is presented in terms of experimental results and experimental measurement method improvements. Also, GENEPI 2, an evolution of the GENEPI concept, is described. This accelerator, is coupled to the PEREN facility which is dedicated to the nuclear cross-section measurements. Last, this paper makes a synthesis of the GENEPI operation feedback at the MASURCA facility and proposes recommendations for future projects involving accelerators used in nuclear reactor environment.Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. -
Article: The GUINEVERE Project for Accelerator Driven System Physics
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ABSTRACT: The GUINEVERE project is part of the EUROTRANS Integrated Project of the 6th EURATOM Framework Programme. It is mainly devoted to ADS on-line reactivity monitoring validation, sub-criticality determination and operational procedures (loading, start-up, shut-down, ...) as a follow-up of the MUSE experiments. The project consists in coupling a fast lead core, set-up in the VENUS reactor at SCK•CEN Mol (B), with a GENEPI neutron source under construction by CNRS. To accommodate the accelerator in a vertical coupling configuration, the VENUS building is being heightened. The fast core will be loaded with enriched Uranium and will be moderated and reflected with solid lead (zero power experiment). For the purpose of the experimental programme, the neutron source has to be operated not only in pulsed mode but also in continuous mode to investigate the current-to-flux reactivity indicator in representative conditions of a powerful ADS. In this latter mode it is also required to make short beam interruptions to have access to the neutron population decrease as a function of time: from this spectrum it will be possible to apply different analysis techniques such as “prompt decay” fitting techniques and “source jerk” techniques. Beam interruptions will be repeated at a programmable frequency to improve time spectra statistics. Different sub-criticality levels (keff=0.99, 0.97, 0.95, ...) will be investigated in order to obtain a full set of data points for the final overall validation of the methodology. This paper describes the status of the experimental facility assembling, and the foreseen experimental programme to be started. -
Article: Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques
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ABSTRACT: Investigations of spectrum adjustment by unfolding techniques for different locations of critical and driven subcritical MUSE4 configurations are presented. The current analysis is based on the recent accomplishment of specific foil activation measurements and on the use of the unfolding code STAY'SL in conjunction with IRDF-90 and IRDF-2002 dosimetry libraries. Specific developments have been conducted to consider the uncertainties associated with the determination of the experimental absolute reaction rates and the initial calculated spectrum in the most realistic manner. In this context, the iterative adjustment process for the neutron spectrum is established on the basis of variance/covariance matrices defined for the three types of input parameters, i.e., the experimental reaction rates, the initial spectrum, and the dosimetry nuclear data files. The results highlight the spectral variations between different locations of the MUSE4 cores, in particular the characteristic behavior of a subcritical configuration driven by an external T(d,n)He 4 (14 MeV neutrons) source. Copyright 2006 by ASTM International. -
Article: Some highlights of experimental ADS programs in Europe
1st International Workshop on Acceleratir-Driven Sub-critical Systems & Thorium Utilization. -
Article: The GUINEVERE project at the VENUS facility
