Analysis of the AMMON Experimental Program in the EOLE Facility Supporting the Qualification of the JHR Neutron and Photon Tools

Vaglio–Gaudard, C.; Colombier, A. C.; Hudelot, Jean-Pascal; Leray, O.; Lemaire, Matthieu; Sergeyeva, V.; Salvo, J. Di; Gruel, A.; Siréta, P.

doi:10.1109/tns.2014.2306440

Cited by 7 publications

(6 citation statements)

References 13 publications

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“…The latter calculations were performed with the TRIPOLI4 Monte Carlo code [8], using a full three-dimensional representation of the AMMON core in the "hafnium" configuration [9]. For better understanding of the following graphs, all measurements were made clockwise with respect to Fig.…”

Section: Resultsmentioning

confidence: 99%

Local Neutron Flux Distribution Measurements by Wire-Dosimetry in the AMMON Experimental Program in the EOLE Reactor

Gruel

Salvo

Roche

et al. 2016

EPJ Web of Conferences

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Abstract. Dosimetry measurements were carried out during the AMMON experimental program, in the EOLE facility. Al-0.1 wt% Au wires were positioned along curved fuel plates of JHR-type assemblies to investigate the azimuthal and axial gold capture rate profiles, directly linked to the thermal and epithermal flux. After irradiation, wires were cut into small segments (a few mm), and the gold capture rate of each part was measured by gamma spectrometry on the MADERE platform. This paper presents results in the "hafnium" configuration, and more specifically the azimuthal flux profile characterization. The final uncertainty on each measured wire lies below 1% (at 2 standard deviations). Experimental profiles are in a good agreement against Monte Carlo calculations, and the 4% capture rate increase at the plate edge is well observed. The flux dissymmetry due to assembly position in the core is also measured, and shows a 10% discrepancy between the two edges of the plate.

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Section: Resultsmentioning

confidence: 99%

Local Neutron Flux Distribution Measurements by Wire-Dosimetry in the AMMON Experimental Program in the EOLE Reactor

Gruel

Salvo

Roche

et al. 2016

EPJ Web of Conferences

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“…A systematic underestimation of the calculated global photon energy deposition is still remaining but has been reduced drastically from about -20% ± 13 % to -8 % ± 4.5 % (1σ) [18]. This underestimation could be partially explained by an underestimation in the JEFF3 prompt photon emission ( 235 U(n,f)) and for 27 Al neutron interactions in the sensor surrounding [18]. However, concerning measurement process itself, low level of covariance data information and lack of recent reevaluated data in EEDL, EPDL, EADL and EXDL limits uncertainty derivation.…”

Section: Gamma Measurementsmentioning

confidence: 97%

“…Since the end of the 90s, CEA has upgraded this method for in EOLE and MINERVE facilities [18] for experimental validation of neutron/gamma calculation schemes used for reactor core modelling.…”

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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“…Thorough representativeness studies have been previously conducted for the transposition of biases to JHR neutron parameters calculations [26,27], based on the representativity method [28]. However, this method cannot be applied in a straightforward manner for photon heating as it requires propagation calculations of a priori uncertainties.…”

Section: Representativeness Of Ammon Core Regarding Jhr Corementioning

confidence: 99%

“…In aluminum, all the activation gamma spectra almost consist of a single 1.78 MeV gamma ray carrying 99% of the total energy. The 1.78 MeV ray corresponds to the gamma ray emitted by beta decay of 28 Al, itself produced by radiative capture of 27 Al.…”

Section: Activation Dosementioning

confidence: 99%

Experimental validation of photon-heating calculation for the Jules Horowitz Reactor

Lemaire

Vaglio–Gaudard

Lyoussi

et al. 2015

Nuclear Instruments and Methods in Physics Research Section A:

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Analysis of the AMMON Experimental Program in the EOLE Facility Supporting the Qualification of the JHR Neutron and Photon Tools

Cited by 7 publications

References 13 publications

Local Neutron Flux Distribution Measurements by Wire-Dosimetry in the AMMON Experimental Program in the EOLE Reactor

Local Neutron Flux Distribution Measurements by Wire-Dosimetry in the AMMON Experimental Program in the EOLE Reactor

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

Experimental validation of photon-heating calculation for the Jules Horowitz Reactor

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