Measurement of photon flux with a miniature gas ionization chamber in a Material Testing Reactor

Fourmentel, D.; Filliatre, P.; Villard, J-F.; Lyoussi, A.; Reynard-Carette, C.; Carcreff, H.

doi:10.1016/j.nima.2013.04.083

Cited by 22 publications

(15 citation statements)

References 12 publications

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“…irradiation box at close proximity. [29], as well as for TLD detectors, where some can be loaded with natural lithium and others with enriched 7 Li. However, qualifying the RadFETs and their temperature dependence [30] is still in progress, and solutions such as different oxide layer thickness and encapsulation of detectors with a neutron filter such as Cd, or by increasing γ production by applying a thin layer of B on the RadFET surface [31] are under investigation.…”

Section: Gamma Field Measurementsmentioning

confidence: 99%

Characterization of gamma field in the JSI TRIGA reactor

et al. 2018

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Abstract-Research reactors such as the "Jožef Stefan" Institute TRIGA reactor have primarily been designed for experimentation and sample irradiation with neutrons. However recent developments in incorporating additional instrumentation for nuclear power plant support and with novel high flux material testing reactor designs, γ field characterization has become of great interest for the characterization of the changes in operational parameters of electronic devices and for the evaluation of γ heating of MTR's structural materials in a representative reactor γ spectrum. In this paper, we present ongoing work on γ field characterization both experimentally, by performing γ field measurements, and by simulations, using Monte Carlo particle transport codes in conjunction with R2S methodology for delayed γ field characterization.

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Section: Gamma Field Measurementsmentioning

confidence: 99%

Characterization of gamma field in the JSI TRIGA reactor

et al. 2018

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“…Hence the thickness of surrounding material in which nuclear heating is measured must be sufficient to reach the charged particles equilibrium (CPE) in the detectors [3]. Ionization chambers can also be used for flux measurements [4]. Among these techniques, two are particularly suitable for photon heating measurements in ZPR, since they do not depend on the photon energy over the reactor photon spectrum (see Fig.…”

Section: Technical Background and Issues Of Nuclear Heating Measurementsmentioning

confidence: 99%

“…At the Experimental Physics Division of CEA Cadarache, the photon heating measurement methodology is 4 Fast Breeder Blanket Facility (Purdue University, Indiana, US). 5 Zero Energy Breeder Reactor Assembly (Winfrith, UK).…”

Section: General Commentsmentioning

confidence: 99%

State of the art on nuclear heating measurement methods and expected improvements in zero power research reactors

Guillou

Gruel

Destouches

et al. 2017

EPJ Nuclear Sci. Technol.

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Abstract. The paper focuses on the recent methodological advances suitable for nuclear heating measurements in zero power research reactors. This bibliographical work is part of an experimental approach currently in progress at CEA Cadarache, aiming at optimizing photon heating measurements in low-power research reactors. It provides an overview of the application fields of the most widely used detectors, namely thermoluminescent dosimeters (TLDs) and optically stimulated luminescent dosimeters. Starting from the methodology currently implemented at CEA, the expected improvements relate to the experimental determination of the neutron component, which is a key point conditioning the accuracy of photon heating measurements in mixed n-g field. A recently developed methodology based on the use of 7 Li and 6 Li-enriched TLDs, precalibrated both in photon and neutron fields, is a promising approach to deconvolute the two components of nuclear heating. We also investigate the different methods of optical fiber dosimetry, with a view to assess the feasibility of online photon heating measurements, whose primary benefit is to overcome constraints related to the withdrawal of dosimeters from the reactor immediately after irradiation. Moreover, a fibered setup could allow measuring the instantaneous dose rate during irradiation, as well as the delayed photon dose after reactor shutdown. Some insights from potential further developments are given. Obviously, any improvement of the technique has to lead to a measurement uncertainty at least equal to that of the currently used methodology (∼5% at 1s).

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“…5). In the case of small thickness of the jacket, the head of the calorimeter 05005-p. 5 would be surrounded only by nitrogen and the energy deposition in the graphite would decrease considerably. According to this study, optimal electronic equilibrium conditions can be reached for a 1.7 mm thickness of steel jacket.…”

Section: Influence Of the Thickness Of The Steel Jacketmentioning

confidence: 99%

“…The second objective is to optimize the measurement method to quantify nuclear heating in these experiments: Radiometric calorimeter (the sensor and the calibration method). The first prototype was already developed and two irradiation campaigns were performed successfully in the CEA MTR OSIRIS in 2012 for nuclear heating levels up to 2 W.g −1 [1,5]. This prototype includes two mock-ups dedicated respectively to photonic measurements (CARMEN-1P) or neutronic measurements (CARMEN-1N) and contains a specific differential calorimeter [6].…”

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

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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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Measurement of photon flux with a miniature gas ionization chamber in a Material Testing Reactor

Cited by 22 publications

References 12 publications

Characterization of gamma field in the JSI TRIGA reactor

Characterization of gamma field in the JSI TRIGA reactor

State of the art on nuclear heating measurement methods and expected improvements in zero power research reactors

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

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