New evaluation of photon production for JEFF-3

Ravaux, S.; Bernard, D.; Santamarina, A.

doi:10.1051/epjconf/20134204002

Cited by 4 publications

(3 citation statements)

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“…Nevertheless, some data were missing (no photon production for all neutron interaction for Gd, Cd, Ag, In, which are nuclei of particular interest for JHR and PWR, no spectrum of the prompt gamma emitted by fission of 239,241 Pu) or inconsistent ( 54,56,57,58 Fe, 62 Ni) [3], or based on quite old measurements (prompt fission gamma emission of 235 U). A new evaluation for radiative capture and inelastic scattering is proposed.…”

Section: Nuclear Data Productionmentioning

confidence: 99%

“…The nuclear data library fails in giving accurate evaluation for photon production of Fe isotopes and 62 Ni (see chapter 2). The PERLE experiment will allow qualifying new data evaluations for these isotopes [3]. Moreover, a recommended method for the total gamma heating one step calculation will be developed with The Monte Carlo simulation code TRIPOLI-4 © with the objective to evaluate directly the deposited energy within the whole geometry.…”

Section: -P3 the Gamma Heating Measurements Are Done With Thermmentioning

confidence: 99%

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Nuclear data production, calculation and measurement: a global overview of the gamma heating issue

Colombier

Amharrak

Fourmentel

et al. 2013

EPJ Web of Conferences

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Section: Nuclear Data Productionmentioning

confidence: 99%

Section: -P3 the Gamma Heating Measurements Are Done With Thermmentioning

confidence: 99%

Nuclear data production, calculation and measurement: a global overview of the gamma heating issue

Colombier

Amharrak

Fourmentel

et al. 2013

EPJ Web of Conferences

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“…Monte Carlo codes such as Serpent 2 [5] have been improved to include coupled neutron-photon transport modes [6] that allow for mixed neutron gamma field calculations, * e-mail: vincent.lamirand@epfl.ch with improvements to energy deposits and delayed particle transport [7] added recently. However, many nuclear data libraries do not include all relevant prompt or delayed emission data [8] in order to provide the full picture [9]. As the delayed contribution of the total gamma flux, or delayed gamma fraction, is typically of the order of 30% [3,[10][11][12], the knowledge and accurate experimental determination of this fraction can aid in validating these codes.…”

Section: Introductionmentioning

confidence: 99%

Delayed gamma fraction determination in the zero power reactor CROCUS

Pakari

Mager

Lamirand

et al. 2021

EPJ Nuclear Sci. Technol.

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Gamma rays are an inextricable part of a nuclear reactor’s radiation field, and as such require characterization for dose rate estimations required for the radiation protection of personnel, material choices, and the design of nuclear facilities. Most commonplace radiation transport codes used for shielding calculations only included the prompt neutron induced component of the emitted gamma rays. The relative amount of gamma rays that are emitted from delayed processes – the delayed gamma fraction – amount to a significant contribution, e.g. in a typical zero power reactor at steady state is estimated to be roughly a third. Accurate predictions of gamma fields thus require an estimation of the delayed content in order to meaningfully contribute. As a consequence, recent code developments also include delayed gamma sources and require validation data. The CROCUS zero power research reactor at EPFL is part of the NEA IRPhE and has therefore been characterized for benchmark quality experiments. In order to provide the means for delayed gamma validation, a dedicated experimental campaign was conducted in the CROCUS reactor using its newly developed gamma detection capabilities based on scintillators. In this paper we present the experimental determination of the delayed gamma fraction in CROCUS using in-core neutron and gamma detectors in a benchmark reactor configuration. A consistent and flexibly applicable methodology on how to estimate the delayed gamma fraction in zero power reactors has hitherto not existed – we herein present a general experimental setup and analysis technique that can be applied to other facilities. We found that the build-up time of relevant short lived delayed gamma emitters is likely attributed to the activation of the aluminium cladding of the fuel. Using a CeBr3 scintillator in the control rod position of the CROCUS core, we determined a delayed gamma fraction of (30.6±0.6)%.

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