Analysis and Recent Advances in Gamma Heating Measurements in MINERVE Facility by Using TLD and OSLD Techniques

Amharrak, H.; Salvo, J. Di; Lyoussi, A.; Roche, A.; Masson-Fauchier, M.; Pepino, A.; Bosq, J. C.; Carette, M.

doi:10.1109/tns.2012.2197637

Cited by 30 publications

(11 citation statements)

References 17 publications

(20 reference statements)

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“…Indeed the expected nuclear heating rate is about 20 W.g −1 for nominal capacity of 100 MW [1], against currently 13 W.g −1 in the irradiation OSIRIS reactor at CEA-Saclay [2]. This level of nuclear heating rate should be compared with measurements performed in critical mock-up reactors of very low power, such as MINERVE and EOLE at the CEA/Cadarache, where nuclear heating reach a value from 10 −7 to 10 −6 W.g −1 [3,4].…”

Section: Introductionmentioning

confidence: 92%

“…Therefore, a another approach to determine this estimation is made in this study by considering another physical parameter which is more representative of heating: the mass energy deposition by the generated charged particles. The determination of this quantity then requires a more comprehensive neutron-photon-electron mode calculation [3]. This paper focuses on the estimation of the heating due to the prompt gammas by these two quantities (energy deposition and KERMA).…”

Section: Introductionmentioning

confidence: 99%

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Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors

Amharrak

Reynard-Carette

Lyoussi

et al. 2016

EPJ Web of Conferences

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Abstract. 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.

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Section: Introductionmentioning

confidence: 92%

Section: Introductionmentioning

confidence: 99%

Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors

Amharrak

Reynard-Carette

Lyoussi

et al. 2016

EPJ Web of Conferences

Self Cite

View full text Add to dashboard Cite

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“…In ZPR, due to very low level of energy deposition rate, timeintegrated values corresponding to nuclear adsorbed doses are quantified by means of ThermoLuminescent Detectors, and Optically Stimulated Luminescent Detectors [122][123][124][125] in two main steps after calibration: irradiation of the detector in reactor and then post-irradiation measurement treatment. In MTR, the nuclear energy deposition rate is determined online thanks to non-adiabatic calorimeters based on temperature measurements.…”

Section: Nuclear Heating Instrumentationmentioning

confidence: 99%

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Giot

Vermeeren

Lyoussi

et al. 2017

EPJ Nuclear Sci. Technol.

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Abstract. The ANIMMA conferences offer a unique opportunity to discover research carried out in all fields of nuclear measurements and instrumentation with applications extending from fundamental physics to fission and fusion reactors, medical imaging, environmental protection and homeland security. After four successful editions of the Conference, it was decided to prepare a review based to a large extent but not exclusively on the papers presented during the first four editions of the conference. This review is organized according to the measurement methodologies: neutronic, photonic, thermal, acoustic and optical measurements, as well as medical imaging and specific challenges linked to data acquisition and electronic hardening. The paper describes the main challenges justifying research in these different areas, and summarizes the recent progress reported. It offers researchers and engineers a way to quickly and efficiently access knowledge in highly specialized areas.

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“…The measured light intensity is detected by a photomultiplier tube in the reader and is directly proportional to the energy deposited by electrons/positrons in the crystal. Measurement Method is described in detail in [13,14]. The measurement analysis is based on Monte Carlo TRIPOLI4© [15] calculations modelling the core exact three-dimensional geometry.…”

Section: Gamma Measurementsmentioning

confidence: 99%

Review of nuclear data improvement needs for nuclear radiation measurement techniques used at the CEA experimental reactor facilities

Destouches

2016

EPJ Web of Conferences

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Abstract. The constant improvement of the neutron and gamma calculation codes used in experimental nuclear reactors goes hand in hand with that of the associated nuclear data libraries. The validation of these calculation schemes always requires the confrontation with integral experiments performed in experimental reactors to be completed. Nuclear data of interest, straight as cross sections, or elaborated ones such as reactivity, are always derived from a reaction rate measurement which is the only measurable parameter in a nuclear sensor. So, in order to derive physical parameters from the electric signal of the sensor, one needs specific nuclear data libraries. This paper presents successively the main features of the measurement techniques used in the CEA experimental reactor facilities for the on-line and offline neutron/gamma flux characterizations: reactor dosimetry, neutron flux measurements with miniature fission chambers and Self Power Neutron Detector (SPND) and gamma flux measurements with chamber ionization and TLD. For each technique, the nuclear data necessary for their interpretation will be presented, the main identified needs for improvement identified and an analysis of their impact on the quality of the measurement. Finally, a synthesis of the study will be done.

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Analysis and Recent Advances in Gamma Heating Measurements in MINERVE Facility by Using TLD and OSLD Techniques

Cited by 30 publications

References 17 publications

Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors

Monte Carlo Simulation Study of a Differential Calorimeter Measuring the Nuclear Heating in Material Testing Reactors

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Review of nuclear data improvement needs for nuclear radiation measurement techniques used at the CEA experimental reactor facilities

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