Neutron heating assessment in Minerve reactor by using alanine/ESR dosimetry

Rouihem, F.; Dridi, W.; Daoudi, M.; Blaise, P.; Geslot, B.; Farah, K.; Mustapha, B.; Hosni, F.

doi:10.1016/j.anucene.2020.107456

Neutron heating assessment in Minerve reactor by using alanine/ESR dosimetry

Journal Article · Fri Mar 13 00:00:00 EDT 2020 · Annals of Nuclear Energy (Oxford)

DOI:https://doi.org/10.1016/j.anucene.2020.107456· OSTI ID:1700686

Rouihem, F. ^[1]; Dridi, W. ^[1]; Daoudi, M. ^[1]; ^[2]; Geslot, B. ^[2]; ^[1]; Mustapha, B. ^[3]; Hosni, F. ^[4]

Centre National des Sciences et Technologie Nucléaires (Tunisia)
Alternative Energies and Atomic Energy Commission (CEA), Cadarache (France)
Argonne National Lab. (ANL), Argonne, IL (United States)
Univ. of Bisha, Bisha (Saudi Arabia)

In the framework of the ICERR (International Center based on Research Reactors) project, the effect of neutron/gamma irradiation on material and dosimeters has been studied. In this work, we explore the alanine dose-response in the core of the MINERVE research reactor at the CEA Cadarache and we investigate the neutron heating effects in order to evaluate alanine neutron sensitivity. The measured dose of the alanine detector in the mixed gamma-neutron field was estimated by electron spin resonance spectrometry (ESR) with reference to an absorbed dose in water from a ⁶⁰Co gamma-ray beam. The experimental sources of uncertainties were reduced by using the optimum conditions of charged-particle equilibrium (CPE), obtained by introducing alanine dosimeters into the aluminum pillbox. Cavity correction factors and dose components were evaluated by the Monte Carlo code MCNP. The calculation showed an underestimated neutron dose with a (C/E) value of about 0.993 +/- 10.83%(k = 1). Results indicate that the fast neutron dose, mainly due to elastic neutron scattering on hydrogen nuclei, represents about 70% of the total dose, while the gamma dose was found to be around 45% of the neutron dose. Additionally, the neutron relative efficiency (REn) to ⁶⁰Co gamma-radiation was estimated to be 0.544 +/- 8%(k = 1).

View Accepted Manuscript (DOE)

Research Organization:: Argonne National Laboratory (ANL), Argonne, IL (United States)

Sponsoring Organization:: USDOE

Contributing Organization:: International Atomic Energy Agency (IAEA); Commissariat a l’Energie Atomique (CEA)

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1700686

Journal Information:: Annals of Nuclear Energy (Oxford), Journal Name: Annals of Nuclear Energy (Oxford) Journal Issue: 107456 Vol. 142; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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