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.; Pépino, A.; Bosq, J. C.; Carette, M.

doi:10.1109/animma.2011.6172901

Cited by 17 publications

(3 citation statements)

References 20 publications

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“…Historically, in-core gamma-ray experiments have relied on flux measurements through devices like thermoluminescent dosimeters (TLDs) [5], ionization chambers [6], or spectrometers placed in regions with a low radiation flux. This is due to reactors' high-flux environments that, even when using high-speed electronics, lead to a significant pulse pile-up and the consequential loss of spectroscopic information [7].…”

Section: Introductionmentioning

confidence: 99%

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Pakari,

Lucas,

Darby

et al. 2024

JNE

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Gamma-ray spectroscopy is an effective technique for radioactive material characterization, routine inventory verification, nuclear safeguards, health physics, and source search scenarios. Gamma-ray spectrometers typically cannot be operated in the immediate vicinity of nuclear reactors due to their high flux fields and their resulting inability to resolve individual pulses. Low-power reactor facilities offer the possibility to study reactor gamma-ray fields, a domain of experiments hitherto poorly explored. In this work, we present gamma-ray spectroscopy experiments performed with various detectors in two reactors: The EPFL zero-power research reactor CROCUS, and the neutron beam facility at the Ohio State University Research Reactor (OSURR). We employed inorganic scintillators (CeBr3), organic scintillators (trans-stilbene and organic glass), and high-purity germanium semiconductors (HPGe) to cover a range of typical—and new—instruments used in gamma-ray spectroscopy. The aim of this study is to provide a guideline for reactor users regarding detector performance, observed responses, and therefore available information in the reactor photon fields up to 2 MeV. The results indicate several future prospects, such as the online (at criticality) monitoring of fission products (like Xe, I, and La), dual-particle sensitive experiments, and code validation opportunities.

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Section: Introductionmentioning

confidence: 99%

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Pakari,

Lucas,

Darby

et al. 2024

JNE

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“…Experiments have also been included in the International Reactor Physics Experimental Evaluation Project (IRPhEP) handbook [11], and the reactor has become a reference center for neutron irradiation of detectors for the ATLAS experiment in CERN [12]. Recent increased interest in development of radiation tolerant electronic devices for operation inside Nuclear Power Plant (NPP) containment buildings [13], particle accelerators [14], aerospace applications [15], [16] and for evaluation of structural material γ heating in Material testing reactors (MTR) [17], [18] has highlighted the need for utilization of reactor irradiation positions for pure γ irradiation. γ-rays inside a nuclear reactor can generally be divided into two groups by their mode of creation: prompt γ-rays, which are produced during reactor operation and are emitted promptly after nucleus interaction, such as fission [19], scattering [20] or radiative capture [21].…”

Section: Introductionmentioning

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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“…The measurement methodology with TLDs implemented at CEA Cadarache is fully described in [3], [4] and [5]- [7], and summed up hereafter. The TLD pellets are usually made of luminescent materials such as doped calcium or lithium fluorides or alumina (CaF 2 , LiF, Al 2 O 3 ).…”

Section: A Overview and General Principlesmentioning

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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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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Analysis and recent advances in gamma heating measurements in MINERVE facility by using TLD and OSLD techniques

Cited by 17 publications

References 20 publications

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Characterization of gamma field in the JSI TRIGA reactor

The CANDELLE Experiment for Characterization of Neutron Sensitivity of LiF TLDs

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