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Assessment of actinide mass embedded in large concrete waste packages by photon interrogation and photofission

  • Published:2005-11 Issue:5-6 Volume:63 Page:613-619
  • ISSN:0969-8043
  • Container-title:Applied Radiation and Isotopes
  • language:en
  • Short-container-title:Applied Radiation and Isotopes

Author:

Gmar M.,Jeanneau F.,Lainé F.,Makil H.,Poumarède B.,Tola F.

Publisher

Elsevier BV

Subject

Radiation

Reference7 articles.

1. MCNP—A General Monte Carlo N-Particle Transport Code—Version 4C,2000

2. Experimental determination of photofission neutron multiplicities for eight isotopes in the mass range 232⩽A⩽239;Caldwell;Nucl. Sci. Eng.,1975

3. MCNPX Extensions Version 2.5.0;Hendricks,2004

4. Huot, N., Gmar, M., 1999. Simulation de l’activation photonique : état d’avancement de l’outil OPERA. CEA internal report (private communication).

5. Lyoussi, A., 1994. Dosage par photofission induite de faibles quantités d’actinides dans les déchets radioactifs enrobés. Thesis.

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1. Characterization of photoneutron fluxes emitted by electron accelerators in the 4–20 MeV range using Monte Carlo codes: A critical review;Applied Radiation and Isotopes;2023-01

2. Feasibility study of the photofission technique for radiological characterization of 220-L concrete-lined nuclear waste drums using 7 or 9 MeV linacs;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2022-04

3. Optimization of a 9 MeV electron accelerator Bremsstrahlung flux for photofission-based assay techniques using PHITS and MCNP6 Monte Carlo codes;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2020-11

4. Active Neutron Monitoring of Nuclear Fuel Cycle Fissile Materials;EPJ Web of Conferences;2020

5. Photofission method for quantification of fissile material in large drums;Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment;2019-12
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