Development and Optimization of Nuclear Heating Measurement Techniques in Zero Power Experimental Reactors

Amharrak, H.; Salvo, J. Di; Lyoussi, A.; Blaise, Patrick; Carette, M.; Roche, A.; Masson-Fauchier, M.; Pépino, A.; Reynard-Carette, C.

doi:10.1109/tns.2014.2355917

Cited by 12 publications

(7 citation statements)

References 26 publications

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“…The standard deviation for TLD-700 is higher because of the very statistics compared to the one of TLD-600 (higher neutron cross-section of 6 Li).…”

Section: Resultsmentioning

confidence: 95%

“…The ratio is obtained from the GC of an uncalibrated TLD-600 irradiated with thermal neutrons, assuming that the gamma contribution for this type of TLD is usually negligible, due to the 6 Li enrichment. The peak heights 1 and 2 are deduced from the TLD-700 calibration GCs in pure gamma field and normalized to dose unit.…”

Section: B Description Of the Gamma-neutron Discrimination Methodsmentioning

confidence: 99%

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The CANDELLE Experiment for Characterization of Neutron Sensitivity of LiF TLDs

Guillou

Billebaud

Gruel

et al. 2018

IEEE Trans. Nucl. Sci.

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Abstract-As part of the design studies conducted at CEA for future power and research nuclear reactors, the validation of neutron and photon calculation schemes related to nuclear heating prediction are strongly dependent on the implementation of nuclear heating measurements. Such measurements are usually performed in low-power reactors, whose core dimensions are accurately known and where irradiation conditions (power, flux and temperature) are entirely controlled. Due to the very low operating power of such reactors (of the order of 100 W), nuclear heating is assessed by using dosimetry techniques such as thermoluminescent dosimeters (TLDs). However, although they are highly sensitive to gamma radiation, such dosimeters are also, to a lesser extent, sensitive to neutrons. The neutron dose depends strongly on the TLD composition, typically contributing to 10-30% of the total measured dose in a mixed neutron/gamma field. The experimental determination of the neutron correction appears therefore to be crucial to a better interpretation of doses measured in reactor with reduced uncertainties. A promising approach based on the use of two types of LiF TLDs respectively enriched with lithium-6 and lithium-7, precalibrated both in photon and neutron fields, has been recently developed at INFN (Milan, Italy) for medical purposes. The CANDELLE experiment is dedicated to the implementation of a pure neutron field "calibration" of TLDs by using the GENEPI-2 neutron source of LPSC (Grenoble, France). Those irradiation conditions allowed providing an early assessment of the neutron components of doses measured in EOLE reactor at CEA Cadarache with 10% uncertainty at 1σ.

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“…The standard deviation for TLD-700 is higher because of the very statistics compared to the one of TLD-600 (higher neutron cross-section of 6 Li).…”

Section: Resultsmentioning

confidence: 95%

Section: B Description Of the Gamma-neutron Discrimination Methodsmentioning

confidence: 99%

The CANDELLE Experiment for Characterization of Neutron Sensitivity of LiF TLDs

Guillou

Billebaud

Gruel

et al. 2018

IEEE Trans. Nucl. Sci.

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“…The measured quantity must therefore previously be qualified in a stable γ source, such as 137 Cs, 60 Co, X-ray and others, preferably high energy sources. CPE is achieved by encapsulating the sensitive part of the detector with an equilibrator part of sufficient thickness [33]. The material of the equilibrator dictates the detector response function, since the actual dose on the equilibrator material is measured.…”

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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“…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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Development and Optimization of Nuclear Heating Measurement Techniques in Zero Power Experimental Reactors

Cited by 12 publications

References 26 publications

The CANDELLE Experiment for Characterization of Neutron Sensitivity of LiF TLDs

The CANDELLE Experiment for Characterization of Neutron Sensitivity of LiF TLDs

Characterization of gamma field in the JSI TRIGA reactor

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

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