Americium-241 phase I: reevaluation for JEFF-3.1.1 and a step forward

Bernard, D.; Bouland, O.

doi:10.1080/18811248.2011.636567

Cited by 8 publications

(3 citation statements)

References 31 publications

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“…Indeed, evaluated cross sections from major libraries differ from 10% to 15%, especially in the thermal domain [1][2][3]. For instance, a difference of 9% on the thermal point can be observed between JEFF-3.2 and ENDF/B-VII.1 nuclear data libraries.…”

Section: Introductionmentioning

confidence: 99%

Americium-241 integral radiative capture cross section in over-moderated neutron spectrum from pile oscillator measurements in the Minerve reactor

et al. 2017

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Abstract. An experimental program, called AMSTRAMGRAM, was recently conducted in the Minerve low power reactor operated by CEA Cadarache within the frame of the CHANDA initiative (Solving CHAllenges in Nuclear Data). Its aim was to measure the integral capture cross section of 241 Am in the thermal domain. Motivation of this work is driven by large differences in this actinide thermal point reported by major nuclear data libraries. The AMSTRAMGRAM experiment, that made use of well characterized EC-JRC americium samples, was based on the oscillation technique commonly implemented in the Minerve reactor. First results are presented and discussed in this article. A preliminary calculation scheme was used to compare measured and calculated results. It is shown that this work confirms a bias previously observed with JEFF-3.1.1 (C/E-1 = −10.5 ± 2%). On the opposite, the experiment is in close agreement with 241 Am thermal point reported in JEFF-3.2 (C/E-1 = 0.5 ± 2%).

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Section: Introductionmentioning

confidence: 99%

Americium-241 integral radiative capture cross section in over-moderated neutron spectrum from pile oscillator measurements in the Minerve reactor

et al. 2017

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“…For example the cross section given by Nakamura et al [14] was derived by assuming g f = 1.05 as recommended by Mughabghab [15]. Using g f = 1 and 0.895 as value for the ratio of the capture cross section to the ground state and the total capture cross section [16], we derive from their data a capture cross section at thermal energy which is in very good agreement with the value obtained in [13]. The resonance parameter file of Lampoudis et al [13] is also consistent with results of integral experiments [17].…”

Section: Resonance Parameters For 241 Am Below 110 Evmentioning

confidence: 99%

Evaluation of Neutron Resonance Cross Section Data at GELINA

Schillebeeckx

Becker

Capote

et al. 2014

Nuclear Data Sheets

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“…The impact of the first four s-wave resonances of 241 Am at 0.3 eV, 0.6 eV, 1.3 eV and 1.9 eV on average integral trend was investigated prior the release of JEFF-3.1. The main motivations for revising the lower part of the 241 Am neutron cross sections were based on integral trends that suggested an increase of the thermal capture cross section and of the epithermal resonance integral [10]. The evaluation work was performed with the SAMMY code by using the total cross sections measured by Belanova [11], Slaughter [12] and Derrien [13] with the transmission technique.…”

Section: From Jeff-30 To Jeff-31mentioning

confidence: 99%

Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2

Noguère

Bernard

Blaise

et al. 2016

Nuclear Science and Engineering

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An overestimation of the k eff values for MOX fuels was identified with Monte-Carlo (TRIPOLI4) and deterministic (APOLLO2) calculations based on the Evaluated Nuclear Data Library JEFF. The overestimation becomes sizeable with the Pu-ageing, reaching a reactivity change of ∆ρ ≃ +700 pcm for integral measurements carried out with MOX fuel containing a large amount of Americium. This bias was observed on various critical configurations performed in the zero power reactor EOLE of the CEA Cadarache, France. The present work focuses on the improvements achieved with the new 239 Pu and 241 Am Evaluated Nuclear Data Files available in the latest version of the JEFF library (JEFF-3.2). The Resolved Resonance Range of the plutonium evaluation was re-evaluated at ORNL (Oak Ridge National Laboratory) with the SAMMY code in collaboration with the CEA Cadarache. The resonance parameters of the Americium evaluation were obtained with the REFIT code in collaboration with the research institutes IRMM

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Americium-241 phase I: reevaluation for JEFF-3.1.1 and a step forward

Cited by 8 publications

References 31 publications

Americium-241 integral radiative capture cross section in over-moderated neutron spectrum from pile oscillator measurements in the Minerve reactor

Americium-241 integral radiative capture cross section in over-moderated neutron spectrum from pile oscillator measurements in the Minerve reactor

Evaluation of Neutron Resonance Cross Section Data at GELINA

Improved Mixed Oxide Fuel Calculations with the Evaluated Nuclear Data Library JEFF-3.2

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