235U and 239PU characterization in radioactive waste using neutron-induced fission delayed gamma rays - CEA - Commissariat à l’énergie atomique et aux énergies alternatives
Communication Dans Un Congrès Année : 2014

235U and 239PU characterization in radioactive waste using neutron-induced fission delayed gamma rays

Résumé

In view of long-term radioactive waste repository, the Differential Die away Technique (DDT) can be used to determine the amount of fissile materials, mainly Pu-239 and U-235, in 225 L bituminized waste drums by detecting prompt and delayed fission neutrons between the pulses of a deuterium tritium neutron generator. A complementary approach studied in this paper is to detect fission delayed gamma rays. Their yields were first measured with bare samples of U-235 and Pu-239 in REGAIN, a facility dedicated to Prompt Gamma Neutron Activation Analysis (PGNAA) at CEA Cadarache, France. Detectability in the 225 L bituminized waste drums is then assessed using the MCNPX model of MEDINA, another PGNAA cell dedicated to 200 L drums at FZJ, Germany. The performances in the bituminized drum are strongly limited by the high gamma count rate due to Cs-137, which imposes the use of collimator and shield, to avoid electronics saturation, and makes the detection of the weak delayed gamma signal impossible. However, promising performances in lower-activity cemented waste drums produced in Germany are currently being studied.
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Dates et versions

cea-04722203 , version 1 (04-10-2024)

Identifiants

  • HAL Id : cea-04722203 , version 1

Citer

Emmanuelle Brackx, B. Perot, Tangi Nicol, C. Carasco, Alain Mariani, et al.. 235U and 239PU characterization in radioactive waste using neutron-induced fission delayed gamma rays. IEEE NUCLEAR SCIENCE SYMPOSIUM AND MEDICAL IMAGING CONFERENCE (NSS/MIC), IEEE, Nov 2014, Seattle, United States. ⟨cea-04722203⟩
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