scholarly journals Bayesian inference of 1D activity profiles from segmented gamma scanning of a heterogeneous radioactive waste drum

2021 ◽  
Vol 175 ◽  
pp. 109803
Author(s):  
Eric Laloy ◽  
Bart Rogiers ◽  
An Bielen ◽  
Sven Boden
1994 ◽  
Vol 118 (3) ◽  
pp. 145-152 ◽  
Author(s):  
R. J. Estep ◽  
T. H. Prettyman ◽  
G. A. Sheppard

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

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

Author(s):  
Aliki van Heek ◽  
Bert Metz ◽  
Bas Janssen ◽  
Ron Groothuis

Most radioactive waste emerges as well-defined waste streams from operating power reactors. The management of this is an on-going practice, based on comprehensive (IAEA) guidelines. A special waste category however consists of the historical waste from research reactors, mostly originating from various experiments in the early years of the nuclear era. Removal of the waste from the research site, often required by law, raises challenges: the waste packages must fulfill the acceptance criteria from the receiving storage site as well as the criteria for nuclear transports. Often the aged waste containers do not fulfill today’s requirements anymore, and their contents are not well documented. Therefore removal of historical waste requires advanced characterization, sorting, sustainable repackaging and sometimes conditioning of the waste. This paper describes the Dutch experience of a historical waste removal campaign from the Petten High Flux research reactor. The reactor is still in operation, but Dutch legislation asks for central storage of all radioactive waste at the COVRA site in Vlissingen since the availability of the high- and intermediate-level waste storage facility HABOG in 2004. In order to comply with COVRA’s acceptance criteria, the complex and mixed inventory of intermediate and low level waste must be characterized and conditioned, identifying the relevant nuclides and their activities. Sorting and segregation of the waste in a Hot Cell offers the possibility to reduce the environmental footprint of the historical waste, by repackaging it into different classes of intermediate and low level waste. In this way, most of the waste volume can be separated into lower level categories not needing to be stored in the HABOG, but in the less demanding LOG facility for low-level waste instead. The characterization and sorting is done on the basis of a combination of gamma scanning with high energy resolution of the closed waste canister and low-resolution localized gamma scanning inside a hot cell. A complicating factor is that the conditioning of the waste, consisting of compacting and cementing, would require such an extensive infrastructure at the Petten site, that it appeared to be more practical to have it executed by a foreign service provider. Therefore the waste packages have to comply with cross-border transport and waste acceptance criteria, and the national legislation of this service provider too. This paper describes this historical waste project, focusing on the fast and precise characterization approach, the expert system behind it, and the sorting and repackaging effort at the Petten site.


2018 ◽  
Vol 15 (35) ◽  
pp. 100-108
Author(s):  
Saad Salih Dawood

The Local manufacturing scanning gamma system designed in Tuwaitha site for nondestructive assay method of radioactive waste drums, where it consist of two main parts with their belongings for controlling the of detector and drum movements up-down and rotation respectively. The volume of the used drum is 220 L with 85 cm height. The drum filled with Portland cement. Six cylindrical holes were made within cement drum and distributed in radial arrangement.The152Eu source inserted in these holes individually, to measure the average angular count rate of gamma radiation. The full energy efficiency value for geometry of drum and detector is computed for thirteen photo peaks. The average efficiency represented by the curve of these peaks indicated the decreasing of efficiency value with increasing the cement thickness and the distance between the detector and the location of radioactive source inside the drum.


Author(s):  
H.-J. Sanden ◽  
G. Caspary ◽  
K. Kroth ◽  
M. Bruggeman ◽  
T. Bücherl

Abstract This paper gives a survey of the main results of research projects performed by members of ENTRAP to improve gamma-ray scanning techniques for radioactive waste packages. Performance characteristics, advantages and restrictions of different assay procedures and correction techniques investigated in these projects are discussed. Case studies are presented which demonstrate the difference in performance between ‘standard’ and ‘improved’ assay techniques. Consideration is also given to bias effects resulting from a limited knowledge on gamma-ray attenuation and/or source distribution in the waste matrix. Procedures and tools are presented which may help to decrease respective bias effects or to assess the overall uncertainty. The achievements emphasise that quality control of assay results requires, in nearly all applications, that additional assay techniques are implemented in order to verify the validity of conventional gamma-ray scanning methods.


2016 ◽  
Vol 63 (6) ◽  
pp. 2793-2800 ◽  
Author(s):  
Weiguo Gu ◽  
Kaiyuan Rao ◽  
Dezhong Wang ◽  
Jiemei Xiong

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