Semi-Tomographic Gamma Scanning Technique for Non-Destructive Assay of Radioactive Waste Drums

2016 ◽  
Vol 63 (6) ◽  
pp. 2793-2800 ◽  
Author(s):  
Weiguo Gu ◽  
Kaiyuan Rao ◽  
Dezhong Wang ◽  
Jiemei Xiong
Author(s):  
J. A. Mason ◽  
W. Hage ◽  
R. Price ◽  
A. C. Tolchard ◽  
A. C. N. Towner

The paper describes an automated non-destructive assay (NDA) system for the measurement and characterization of radioactive waste. The Waste Characterisation System (WCS) can be adapted to measure a variety of drum sizes: 60, 220 (55 gallon) and 440 liter, the latter with a maximum weight of 1500 kg (1.5 tonnes). The NDA system includes a Tomographic Segmented Gamma Scanner (TSGS) and an active/passive neutron Differential Die-away (DDA or DDT). The system can assay a wide variety of waste types in a range of waste matrices. The assay stations are linked by a heavy duty roller conveyor which incorporates a 20 drum buffer store, a load cell (built into the conveyor), bar code readers and a dose rate measurement station. The Tomographic Segmented Gamma Scanner (TSGS) combines conventional high resolution gamma spectrometry and a tranission source to interrogate a waste drum in vertical slices (segments) as for Segmented Gamma Scanner (SGS) measurements. However, in the case of the TSGS, while the drum is rotated, it is also moved in the horizontal direction leading to an enhanced ability to correct the gamma ray energies, from the nuclides of interest, for the attenuation of the matrix. The TSGS can also be operated as a conventional SGS for the measurement of homogeneous waste drums. The DDA is a very sensitive active neutron interrogation method that uses thermalised neutrons from a pulsed source within the chamber to irradiate a waste drum. Prompt neutrons from fissile material present in the waste (e. g. 239Pu, 235U) are detected and provide a measure of the fissile content in the drum. In passive mode, the DDA determines the even Pu nuclides exhibiting significant spontaneous fission (e.g. 240Pu). Measurement accuracy depends on correction algorithms to compensate for self-shielding and matrix effects in waste drums containing hydrogenous materials. In addition, the DDA will be provided with the Fission-Fission Neutron Correlation Analysis System (FFnC) which is an absolute technique eliminating the need for matrix dependent mass calibrations, and allowing separate U and Pu determination using delayed neutron counting. The FFnC technique will be tested for the first time on the WCS. The NDA system incorporates integrated stations to determine the weight and dose rate of each drum, the former built into the conveyor the latter as part of the TSGS. Six Geiger Muller tubes measure the surface dose at three positions on the drum side, one at 1 metre from the drum and one each measuring the surface dose of the top and bottom of the drum. The assay instruments are linked to a heavy duty conveyor system onto which up to 20 waste drums can be loaded for delivery to the various measurement stations, thus permitting unattended, automated operation. Once measured, the drums remain on the conveyer in a holding system waiting to be unloaded. Automation is provided using a programmable logic controller (PLC) and associated computers. A central computer and associated software is used for data acquisition and management.


2020 ◽  
Vol 225 ◽  
pp. 06003
Author(s):  
W. R. Kubinski ◽  
C. Carasco ◽  
D. Kikola ◽  
C. Mathonat ◽  
D. Ricard ◽  
...  

The EU-CHANCE project aims at the issue of the characterization of conditioned radioactive waste (CRW) and one objective of CHANCE is to focus on: Calorimetry as a comprising non-destructive technique to reduce uncertainties on the inventory of radwaste containing shielded and hidden material difficult to be measured by other means. A MCNP6-based numerical study comprising the particle flux out of a 200L mock-up drum in a Large Volume Calorimeter (LVC) currently manufactured by KEP Nuclear (France) will be presented and discussed. For the analyses, the particle flux and energy deposition in each layer of the calorimeter were determined. The results yield that a significant fraction of the radiation would leave the system and not contribute to the measurable heat deposition. The expected energy deposition is obtained and cumulated for each layer over the whole energy range revealing the fraction of particles actually escaping the LVC calorimeter. While this escape fraction needs and can be determined, the LVC is a very suitable apparatus for the anticipated experiments on large and heterogeneous waste drums that possibly contain deeply buried beta-emitters (e.g. Sr/Y-90) or shielded alpha-sources hidden inside the drum with a significant level of gamma and neutron radiation background radiation. The high-energy part of this gamma and neutron flux may even reach the reference chamber of the calorimeter and deposit some energy there, compromising the calibration and may cause a double-bias.


Author(s):  
Ramkumar Venkataraman ◽  
Marcel Villani ◽  
Stephen Croft ◽  
Patricia McClay ◽  
Robert McElroy ◽  
...  

Author(s):  
Jin Beak Park ◽  
Kun Jai Lee ◽  
Duck Won Kang ◽  
Dae Hwan Kim

Abstract In 1996, the fully automated radionuclide assay system, which is used for the non-destructive analysis and for the evaluation of radioactive waste drums, was installed at Kori nuclear power plant site and started to operate. The system is composed of gamma scanning hardware facility, equipment for separation and detection of non-gamma radionuclide, scaling factor prediction program, and control facility for radionuclide assay system. In this study, the operational status and results of radionuclide assay system are investigated from the experience of several years of operation. The results of the radionuclide assay system are compared with the results of dose to curie conversion program (DOSE).


2020 ◽  
Vol 67 (4) ◽  
pp. 544-551
Author(s):  
Eran Vax ◽  
Eliezer Marcus ◽  
Tzahi Mazor ◽  
Yagil Kadmon ◽  
Alon Osovizky

Author(s):  
L. P. M. van Velzen ◽  
M. Bruggeman ◽  
J. Botte

The European Network of Testing Facilities for the Quality Checking of Radioactive Waste Packages (ENTRAP) initiated a feasibility study on how to organize in the most cost effective way an international proficiency tests for non-destructive, gamma-ray based, assay of 220 liter radioactive waste drums in the European Union at a regular time interval of 2 or 3 years. This feasibility study addresses all aspects of proficiency testing on radioactive waste packages including the design of a commonly accepted reference 220 liter drum. This design, based on the international response on a send out questionnaire, includes matrixes, radioactive sources; a solution to overcome the tedious and expensive international transport costs of real or even simulated waste packages, general cost estimation for the organization of, and the participation in the proficiency test. The proposed concept for the proficiency testing and the estimated costs are presented. The participation costs of the first proficiency test are mainly determined by the manufacturing of the non-radioactive 220 liter drum (± 55%). Applied reference sources, transport of the drum and reference sources and participation costs in the proficiency test contribute each about ± 15%.


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