CONRAD – a code for nuclear data modeling and evaluation

Jean, C. De Saint; Tamagno, Pierre; Archier, P.; Noguère, G.

doi:10.1051/epjn/2021011

Cited by 11 publications

(8 citation statements)

References 58 publications

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“…Calculation of means and standard deviations of the detection rates over all runs. The final decay curves are fed to the CONRAD nuclear data evaluation tool [12] to fit the delayed neutron yield expressed as parameters in the theoretical model based on Equations ( 4) and ( 5).…”

Section: Data Processingmentioning

confidence: 99%

Measurement of the delayed-neutron yield in the thermal neutron induced fission of ²³⁹Pu

Sardet

2023

EPJ Web of Conf.

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This article presents an experimental effort to provide high-quality data to improve the evaluation of the 239Pu delayed neutron yield in the thermal energy range. The set-up is composed of a long counter with sixteen 3He tubes, a fast shutter system to produce irradiation cycles with short rising/falling times, and a miniature fission chamber containing 114μg of 239Pu. The whole system was installed in the PF1B experimental zone of the Institut Laue-Langevin, which provides a cold neutron beam. The repetition of irradiation/decay cycles enables to saturate the delayed neutron precursors and to measure their yield through the observed activity, shortly after the beam-stop. The innovation of our measurement technique relies on the clear distinction between prompt and delayed neutron counting, thanks to boron absorbers, without the necessity to move the sample. In such a way, it is possible to normalize the counting of delayed neutron emission to the one of total neutron emission, based on the well-known value of the prompt neutron multiplicity. The present work provides a delayed neutron yield value of vd = 0.642(5)%. The latter is in 1σ agreement with the IAEA recommendation of 0.628(38)%, with a strongly reduced uncertainty thanks to our normalization technique.

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Section: Data Processingmentioning

confidence: 99%

Measurement of the delayed-neutron yield in the thermal neutron induced fission of ²³⁹Pu

Sardet

2023

EPJ Web of Conf.

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“…To fit the 242 Pu fission cross section in the RRR, the code used is the CONRAD code [11], developed at CEA of Cadarache. This code is based on the R-Matrix formalism [9].…”

Section: Evaluation In the Conrad Codementioning

confidence: 99%

Re-examining intermediate resonant structures in the ²⁴²Pu fission cross section

et al. 2023

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The study of the 242Pu fission cross section has become more important since this isotope is present in Pressurized Water Reactor Uranium Oxide and Mixed Oxide fuel, as well as in fast neutron reactors fuel. This nucleus has been also selected for monitoring the high neutron flux RJH reactor (CEA-Cadarache). For all these reasons, the fission cross section structure of this fertile isotope, and especially its class-II states resonances were investigated in this work. Two class-II states have been identified in the Resolved Resonance Range (RRR) and their parameters have been supplied to the CONRAD code. 68 class- II states have been identified in the Unresolved Resonant Range (URR) and their parameters have been added in the TALYS code data library to reproduce as well as possible the experimental fission cross section. The methodology to identify and insert the class-II states in RRR and URR is described here.

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“…However, these were limited to the influence of cross-sections, and continuous energy calculations were limited to specific nuclear parameters (resonance parameters). A recent coupling [3] between the nuclear reaction code CONRAD [4] and a development version of the stochastic code TRIPOLI-4 ® [5] allows calculating full sensitivities of integral experiment reactivity to nuclear parameters, with contributions from all nuclear data, without energy and models restrictions [6,7]. With such tool, we are now able to adjust nuclear parameters and phenomenological models on integral experiment results, and especially here, criticality experiments reactivity.…”

Section: Introductionmentioning

confidence: 99%

Assimilation of integral experiments on high-energy nuclear parameters

2023

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Current assimilation of integral experiments often consists in adjusting multi-group cross sections with feedbacks from critical reference benchmarks. In order to maintain the constraints coming from nuclear models, we present here a method to achieve assimilation of integral experiment on nuclear parameters, from which nuclear data are evaluated. This method, based on Bayesian inference, uses continuous energy reactivity sensitivities to nuclear parameters, throughout all the nuclear data types (cross section, angular distribution, energy distribution, fission multiplicity and spectrum). This improvement was made possible by coupling a stochastic transport code and a nuclear data evaluation code. The study of a test case – the assimilation of Jezebel ICSBEP benchmark on a plutonium-239 toy evaluation – shows that angular and energy distributions have a non-negligible impact on the assimilation process and results.

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CONRAD – a code for nuclear data modeling and evaluation

Cited by 11 publications

References 58 publications

Measurement of the delayed-neutron yield in the thermal neutron induced fission of ²³⁹Pu

Measurement of the delayed-neutron yield in the thermal neutron induced fission of ²³⁹Pu

Re-examining intermediate resonant structures in the ²⁴²Pu fission cross section

Assimilation of integral experiments on high-energy nuclear parameters

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CONRAD – a code for nuclear data modeling and evaluation

Cited by 11 publications

References 58 publications

Measurement of the delayed-neutron yield in the thermal neutron induced fission of 239Pu

Measurement of the delayed-neutron yield in the thermal neutron induced fission of 239Pu

Re-examining intermediate resonant structures in the 242Pu fission cross section

Assimilation of integral experiments on high-energy nuclear parameters

Contact Info

Product

Resources

About

Measurement of the delayed-neutron yield in the thermal neutron induced fission of ²³⁹Pu

Measurement of the delayed-neutron yield in the thermal neutron induced fission of ²³⁹Pu

Re-examining intermediate resonant structures in the ²⁴²Pu fission cross section