Transuranic waste detection by photon interrogation and on-line delayed neutron counting

Lyoussi, A.; Romeyer-Dherbey, J.; Jallu, Fanny; Payan, E.; Buisson, A.; Nurdin, G.; Allano, J

doi:10.1016/s0168-583x(99)00586-8

Cited by 30 publications

(16 citation statements)

References 1 publication

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“…The present numerical simulation involved a two step approach: (1) a time-independent electron-photon transport calculation to obtain energy and angular distributions of bremsstrahlung photons leaking from the converter, and (2) a time-dependent photon-neutron transport calculation to obtain the 3 He detector counts of delayed neutrons.…”

Section: Calculational Methodologymentioning

confidence: 99%

“…14) Figure 1 depicts a schematic view of the proposed active NDA system which is composed of the electron accelerator with a photon collimator and two arrays of 3 He neutron detectors for assaying the re-casted steel waste of a cylindrical shape. This system is housed in an assay room of 8 m length, 4 m width and 4 m height.…”

Section: Overview Of Proposed Systemmentioning

confidence: 99%

“…2,3) The major uranium isotopes have much longer half lives than the other actinides such as plutonium isotopes. This feature of uranium isotopes often makes quantitative determination of them in the waste to be difficult by means of detecting characteristic radiations spontaneously emitted from them with the nondestructive manner.…”

Section: Introductionmentioning

confidence: 99%

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A Conceptual Design Study for Active Nondestructive Assay System by Photon Interrogation for Uranium-Bearing Waste with MVP Code and Evaluated Photonuclear Data

Sakurai

Kosako

Mori

2011

Progress in Nuclear Science and Technology

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A conceptual design study has been carried out with a Monte Carlo transport code on an active nondestructive assay system for low-level uranium-bearing wastes discharged from an uranium enrichment plant. Delayed neutrons from photofissions of uranium isotopes in the steel waste are counted with this system to confirm that the activity concentration of uranium in this waste is below the clearance level. The present design work needs a coupled neutron/photon transport code which can simulate the photonuclear reaction and the resultant emission of neutrons. We have modified a continuous-energy Monte Carlo transport code MVP to equip it with a function to simulate the emission of photoneutrons along with the delayed neutrons from the photofissions. The photonuclear data library for the modified MVP code was prepared on the basis of evaluated photonuclear data by IAEA. For the 235 U and 238 U, we employed evaluated data in the JENDL photonuclear data 2004, which stores complete delayed neutron emission data for these nuclides. With this code system, a time-dependent simulation of neutron counts was made for the assay system, which consisted of a 15 MeV end-point bremsstrahlung photon source, helium-3 neutron detectors and the waste. The present paper describes the modification to the MVP code and the results of design study.

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Section: Calculational Methodologymentioning

confidence: 99%

Section: Overview Of Proposed Systemmentioning

confidence: 99%

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A Conceptual Design Study for Active Nondestructive Assay System by Photon Interrogation for Uranium-Bearing Waste with MVP Code and Evaluated Photonuclear Data

Sakurai

Kosako

Mori

2011

Progress in Nuclear Science and Technology

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“…The most widely used techniques are undeniably active neutron measurement, straight line photon transmission, X-ray gamma fluorescence, transmission tomography, and, to a lesser extent interrogation by induced photofissions [94], photon activation and photofission tomography [95].…”

Section: Active Photon Measurementsmentioning

confidence: 99%

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Giot

Vermeeren

Lyoussi

et al. 2017

EPJ Nuclear Sci. Technol.

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Abstract. The ANIMMA conferences offer a unique opportunity to discover research carried out in all fields of nuclear measurements and instrumentation with applications extending from fundamental physics to fission and fusion reactors, medical imaging, environmental protection and homeland security. After four successful editions of the Conference, it was decided to prepare a review based to a large extent but not exclusively on the papers presented during the first four editions of the conference. This review is organized according to the measurement methodologies: neutronic, photonic, thermal, acoustic and optical measurements, as well as medical imaging and specific challenges linked to data acquisition and electronic hardening. The paper describes the main challenges justifying research in these different areas, and summarizes the recent progress reported. It offers researchers and engineers a way to quickly and efficiently access knowledge in highly specialized areas.

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“…Out of the currently available semiconductors 4H-SiC seems to be the most suitable neutron detector material under extreme conditions due to its high heat and radiation resistance, large band-gap energy and lower production cost than the competing diamond detectors. Some of future using and interesting applications of such SiC detector devices for noncharged particles (photons and/or neutrons) are expected in the frame of nondestructive assays, nuclear reactor monitoring, safeguards, oil, and gas prospections [1]- [3]. Manuscript As a result of several years of development, high quality SiC crystal material are now widely available and may be used to make advanced devices.…”

Section: Introductionmentioning

confidence: 99%

Fast Neutron Detection With 4H-SiC Based Diode Detector up to 500 °C Ambient Temperature

Szalkai

Ferone

Issa

et al. 2016

IEEE Trans. Nucl. Sci.

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In the framework of the European I-Smart project, optimal 4H-SiC based diode geometries were developed for high temperature neutron detection. Irradiation tests were conducted with 14 MeV fast neutrons supplied by a deuteriumtritium neutron generator with an average neutron yield of 4.04 × 10 10 − 5.25 × 10 10 n/s at Neutron Laboratory of the Technical University of Dresden in Germany. In this paper, we interpret the first measurements and results with 4H-SiC detector irradiated with fast neutrons from room temperature up to 500 • C. These experiments are serving also the first simulation of the harsh environmental condition measurements in the tritium breeding blanket of the ITER fusion reactor, which is one of the most prominent planned location of high temperature neutron flux characterization studies in the near future.

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Transuranic waste detection by photon interrogation and on-line delayed neutron counting

Cited by 30 publications

References 1 publication

A Conceptual Design Study for Active Nondestructive Assay System by Photon Interrogation for Uranium-Bearing Waste with MVP Code and Evaluated Photonuclear Data

A Conceptual Design Study for Active Nondestructive Assay System by Photon Interrogation for Uranium-Bearing Waste with MVP Code and Evaluated Photonuclear Data

Nuclear instrumentation and measurement: a review based on the ANIMMA conferences

Fast Neutron Detection With 4H-SiC Based Diode Detector up to 500 °C Ambient Temperature

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