Characterization of the neutron field from the 241Am-Be isotopic source of the IPHC irradiator

Amgarou, K.; Trocmé, M.; García-Fusté, M.J.; Vanstalle, M.; Baussan, E.; Nourreddine, A.; Domingo, C.

doi:10.1016/j.radmeas.2012.11.015

Cited by 10 publications

(5 citation statements)

References 23 publications

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“…The neutron fluence rate  and H*(10) calculated using the MCNPX code [13] through a point detector (F5 tally) for the same distance are 43.5  0.5 cm -2 s -1 and 50.6  0.5 µSv h -1 , respectively. These values are to be compared with the values of 41.0  1.9 cm -2 s -1 and 48.8  2.4 µSv h -1 obtained by Bonner sphere spectrometry [12]. For our simulation, the 241 Am-Be source structure was taken as reported by the supplier [14] and the neutron energy distribution (4•10 -7  E n  10 MeV) with an average neutron energy of 4.4 MeV was provided by ISO 8529-1 [15].…”

Section: Irradiation Conditionsmentioning

confidence: 97%

“…The neutron irradiations were performed with the laboratory's 241 Am-Be calibrator. The neutron source intensity is estimated to be (2.24  0.12)  10 6 s -1 , determined by Bonner sphere spectrometry [12] for an ambient neutron dose equivalent rate H*(10) of 48.8  2.4 µSv h -1 at 75.0  0.1 cm. The neutron fluence rate  and H*(10) calculated using the MCNPX code [13] through a point detector (F5 tally) for the same distance are 43.5  0.5 cm -2 s -1 and 50.6  0.5 µSv h -1 , respectively.…”

Section: Irradiation Conditionsmentioning

confidence: 99%

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Present state of the art of a fast neutron dosimeter incorporating RPL detectors

NOURREDDİNE¹

2015

Journal of Nuclear Sciences

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The recently introduced radiophotoluminescent (RPL) detectors offer a unique combination of advantages for radiation monitoring that include rapid exploitation, stability to fading, reusability, and insensitivity to light, temperature and humidity. We look at the behavior of an RPL-based fast neutron dosimeter capable of measuring neutrons in an n- field. The tested dosimeter consists of an ordered assembly of Al foil, RPL detector (I), Al foil, polyethylene converter, RPL detector (II) and Al foil encased in a polyethylene container. The difference between the two RPL configurations represents the (n,p) protons and is related to the fast neutron dose. The dosimeter response is linear and shows an acceptable angular dependence. However the measured detection threshold for this dosimeter is too high for routine monitoring. This threshold could be lowered at to a more practicable value if next generation improvements in RPL detectors and the reader are applied. The main shortcomings we encountered are (i) a 1.7 µm thick dead layer at the front surface of the detectors that render them insensitive to a large fraction of the recoil protons and (ii) an intrinsic detector background that could be reduced if the reader were able to separate individual densely ionized zones created by the recoil protons from the -ray signal.

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Section: Irradiation Conditionsmentioning

confidence: 97%

Section: Irradiation Conditionsmentioning

confidence: 99%

Present state of the art of a fast neutron dosimeter incorporating RPL detectors

NOURREDDİNE¹

2015

Journal of Nuclear Sciences

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“…Two samples were irradiated with the AmBe source: Au and V. The isotropic 241 Am-Be neutron source used has an activity of 3.7 × 10 10 Bq and a nominal neutron emission rate of 2.24 × 10 6 n/s [21]. The AmO2-Be powder is doubleencapsulated within welded stainless-steel cylinders, which are inside of a Pb cylinder.…”

Section: A Direct Neutron Fieldmentioning

confidence: 99%

Validation of Monte Carlo simulations by experimental measurements of neutron-induced activation in cyclotrons

Collin,

Horodynski,

Arbor

et al. 2023

EPJ Web Conf.

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Nuclear activation is the process of production of radionuclides by irradiation. This phenomenon concerns particle accelerators used in various fields, from medical applications to industrial ones, both during operation and at the decommissioning phase. For more than three decades, the possibility of using cyclotrons for nuclear power generation and nuclear waste reduction has also been discussed, i.e. in the case of Accelerator-Driven Systems [1]. The radioprotection and dismantling issues of accelerator facilities, that have been raised recently, is even more potent for such installations. In our study, we are particularly interested in the activation due to secondary neutrons produced by (x,n) reactions, mostly (p,n) occurring in the accelerator’s components. This work focuses on the study of the radioactivity induced in various materials (V, Sc, Tb, W, Ta) irradiated by fast and thermal neutrons, in two different scenarios: through direct irradiation -with an AmBe sourceand around an operating cyclotron at the CYRCé facility (Strasbourg). A broad Monte Carlo study including FLUKA, GEANT4, PHITS and MCNP simulation has been performed, with and without a FISPACT-II coupling, to estimate the reaction rates and to trace the induced radioactivity in samples of known composition. The results of the simulations are compared with the values extracted in two dedicated experimental campaigns in which activated samples underwent high resolution gamma-ray spectrometry.

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“…Many experimental results demonstrated the methodology soundness in the field of neutron studies. Some groups employed Nuclear Track Detectors (NTD) [1,2] in neutron beam dosimetry, extending the technique first to neutron field mapping [3,4], and later for radiography and radiation protection [5,6,7,8], neutron induced nuclear recoils events by CR-39 polycarbonate and more recently it was applied in fast neutron spectrometry [9]. Based on the referenced information and driven by experience it was considered an important initiative to determine NTD response and limitation to determine characteristic neutron flux of Triga Mark III reactor as a function of the operating power.…”

Section: Introductionmentioning

confidence: 99%

Changes of the Neutron Flux of the Nuclear Reactor Triga Mark III Since the Conversion from High to Low 235U Enrichment

Vázquez-López

Ángel-Gómez

Raya-Arredondo

et al. 2021

J. Nucl. Phy. Mat. Sci. Rad. A.

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The neutron flux of the Triga Mark III research reactor was studied using nuclear track detectors. The facility of the National Institute for Nuclear Research (ININ), operates with a new core load of 85 LEU 30/20 (Low Enriched Uranium) fuel elements. The reactor provides a neutron flux around 2 × 1012 n cm-2s-1 at the irradiation channel. In this channel, CR-39 (allyl diglycol policarbonate) Landauer® detectors were exposed to neutrons; the detectors were covered with a 3 mm acrylic sheet for (n, p) reaction. Results show a linear response between the reactor power in the range 0.1 - 7 kW, and the average nuclear track density with data reproducibility and relatively low uncertainty (±5%). The method is a simple technique, fast and reliable procedure to monitor the research reactor operating power levels.

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Characterization of the neutron field from the 241Am-Be isotopic source of the IPHC irradiator

Cited by 10 publications

References 23 publications

Present state of the art of a fast neutron dosimeter incorporating RPL detectors

Present state of the art of a fast neutron dosimeter incorporating RPL detectors

Validation of Monte Carlo simulations by experimental measurements of neutron-induced activation in cyclotrons

Changes of the Neutron Flux of the Nuclear Reactor Triga Mark III Since the Conversion from High to Low 235U Enrichment

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