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

被引：0

作者：

Nicol, T. ^{[1
]}

Perot, B. ^{[1
]}

Carasco, C. ^{[1
]}

Brackx, E. ^{[2
]}

Mariani, A. ^{[1
]}

Passard, C. ^{[1
]}

Mauerhofer, E. ^{[3
]}

Collot, J. ^{[4
]}

机构：

[1] CEA, DEN, Nucl Measurement Lab, F-13108 St Paul Les Durance, France

[2] CEA, DEN, Metallog & Chem Anal Lab, F-30207 Bagnols Sur Ceze, France

[3] FZJ, Inst Energy & Climate Res Nucl Waste Management &, D-52428 Julich, Germany

[4] Univ Grenoble Alpes, CNRS, IN2P3, Lab Phys Subat & Cosmol, Grenoble, France

来源：

2014 IEEE NUCLEAR SCIENCE SYMPOSIUM AND MEDICAL IMAGING CONFERENCE (NSS/MIC) | 2014年

关键词：

fission; delayed gamma; radioactive waste characterization; MCNPX simulation; IDENTIFICATION; SIGNATURES; ACTINIDES; PACKAGES;

D O I：

暂无

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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.

引用

页数：6

共 22 条

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