scholarly journals Gamma—Ray Counters to Monitor Radioactive Waste Packages in the MICADO Project

Instruments ◽  
2021 ◽  
Vol 5 (2) ◽  
pp. 19
Author(s):  
Luigi Cosentino ◽  
Martina Giuffrida ◽  
Sergio Lo Meo ◽  
Fabio Longhitano ◽  
Alfio Pappalardo ◽  
...  

One of the goals of the MICADO Euratom project is to monitor the gamma-rays emitted by radioactive waste drums in storage sites on a medium to long term basis. For this purpose, 36 low-cost gamma-ray counters were designed and built to act as a demonstrator. These counters, named SciFi, are based on a scintillating fiber readout at each end by a silicon photomultiplier, assembled in a robust arrangement in the form of 80 cm long pipes. Several counters will be placed around radwaste packages in order to monitor the gamma dose-rate by collecting a continuous data stream. The 36 sensors were thoroughly tested with a 22Na and a 137Cs gamma-ray sources, and with an AmBe neutron and gamma-ray source, the results are quite satisfactory, and the next step will be the test in a real environment.


2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Jihwan Boo ◽  
Mark D. Hammig ◽  
Manhee Jeong

AbstractDual particle imaging, in which both neutrons and gamma-rays in the environment can be individually characterized, is particularly attractive for monitoring mixed radiation emitters such as special nuclear materials (SNM). Effective SNM localization and detection benefits from high instrument sensitivity so that real-time imaging or imaging with a limited number of acquired events is enabled. For portable applications, one also desires a dual particle imager (DPI) that is readily deployable. We have developed a hand-held type DPI equipped with a pixelated stilbene-silicon photomultiplier (SiPM) array module and low sampling-rate analog-to-digital converters (ADCs) processed via a multiplexed readout. The stilbene-SiPM array (12 × 12 pixels) is capable of effectively performing pulse shape discrimination (PSD) between gamma-ray and neutron events and neutron/gamma-ray source localization on the imaging plane, as demonstrated with 252Cf neutron/gamma and 137Cs gamma-ray sources. The low sampling rate ADCs connected to the stilbene-SiPM array module result in a compact instrument with high sensitivity that provides a gamma-ray image of a 137Cs source, producing 6.4 μR/h at 1 m, in less than 69 s. A neutron image for a 3.5 × 105 n/s 252Cf source can also be obtained in less than 6 min at 1 m from the center of the system. The instrument images successfully with field of view of 50° and provides angular resolution of 6.8°.



Author(s):  
F.-W. Ledebrink ◽  
P. Faber

Abstract In the period since Germany’s experimental final repository ASSE was closed in 1978, around 5000 drums of conditioned plutonium-bearing radioactive waste from mixed-oxide (MOX) fuel fabrication have accumulated in the interim storage facilities of Siemens AG’s MOX fuel fabrication plant in Hanau, Germany — formerly ALKEM GmbH, now Siemens Decommissioning Projects (Siemens DP). Another 5000 drums will arise in the course of decommissioning and dismantling the MOX plant which has now been underway for some months. Hopes that a final waste repository would soon be able to go into operation in Germany have remained unfulfilled over the last 20 years. Also, the agreements reached between Germany’s electric utilities and the Federal Government regarding the future of nuclear energy have not led to any further progress in connection with the issue of radwaste disposal. A concrete date for a final repository to start operation has still not been set. The German Federal Government estimates that a geologic repository will not be needed for at least another 30 years. Since the opening of a final storage facility is not foreseeable in the near term, Siemens is taking the necessary steps to enable radwaste to be safely stored in aboveground interim storage facilities for a prolonged period of time. Conditioning of radwaste from MOX fuel fabrication by cementing it in drums was started in 1984 in the belief — which was justified at that time — that final storage at the Konrad mine would be possible as of 1995. The quality requirements specified for the waste drums were therefore based on the Konrad acceptance criteria. The operating license for the storage facilities at Hanau at which these drums are presently in interim storage is limited to 20 years and will be expiring in 2004. The drums have not suffered any corrosion to date and, according to past experience, are not expected to do so in the future. However, permission to keep the drums in interim storage for a longer period of time in their current form would be extremely difficult to obtain as their corrosion resistance would have to be demonstrated for a further 30 years. The present goal is therefore to create a waste form suitable for interim storage which needs no maintenance over a long-term period, incorporates state-of-the-art technology and will probably not require any further treatment of the waste packages prior to emplacement in a final storage facility. At the same time, the highest possible degree of safety must be assured for the time during which the waste remains in interim storage. This goal can be attained by conditioning the drums such that they satisfy the requirements currently specified for final storage at the Konrad repository (1). In practice, this means immobilizing the cemented waste drums in concrete inside steel “Konrad Containers” (KCs). The KCs themselves and the concrete backfill represent two further barriers which not only serve as radiation shielding but also protect the drums against corrosion as well as any possible release of radioactive materials in the event of accidents occurring during interim storage. As the KCs are cuboid in shape, they can be stacked in space-saving configurations and are thus particularly suitable for interim storage. Also, due to their extremely heavy weight, theft of the waste packages can be practically ruled out. Despite the fact that the agreements with the German Federal Government have failed to bring opening of the Konrad repository within reach, it is nevertheless a good idea today to condition radwaste in a manner that renders it suitable for ultimate storage there. The agreements between the Government and the utilities are expected at least to result in a land use permit being issued for the Konrad mine before the end of 2001. At present there are no facts known that could cause the safety of this facility to be questioned. Only recently, Germany’s International Nuclear Technology Commission (ILK) confirmed Konrad’s suitability and demanded that it be placed in operation without further delay (2). Even if its operation should, in fact, be blocked by political lobbies, potential legal action or economic considerations, the alternative repository at Gorleben could possibly become operable in approximately 30 years’ time. Gorleben was planned right from the start to be able to accommodate waste packages based on the Konrad acceptance criteria. This means that any waste packages designed for storage at Konrad could likewise be handled and stored at Gorleben. The processes used by Siemens for conditioning of radwaste conform to the recommendations of the “Guidelines for the Control of radioactive Waste with negligible Heat Generation” issued by the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU) in 1989 (3).



Author(s):  
Bertrand Perot ◽  
Jean-Luc Artaud ◽  
Bernard Chabalier ◽  
Pierre Bonifay ◽  
Sébastien Bernard ◽  
...  

Abstract The determination by gamma spectroscopy of the activity of radionuclides emitting low energy radiation (less than 200 keV) in bituminized waste drums can be affected by significant uncertainty if the chemical composition of the matrix is not well-known. Indeed, some elements with high atomic numbers (Z) can significantly modify the absorption of these radiations. The CEA has therefore studied, using numerical simulation, the feasibility of a method which would take into account this effect, based on the analysis of the gamma spectra continuum due to Compton scattering (1). This article describes an experimental validation of the simulations and of the method.



1982 ◽  
Vol 9 (1) ◽  
pp. 27-30
Author(s):  
Harold E. Pattee ◽  
Francis G. Giesbrecht ◽  
James W. Dickens ◽  
Johnny C. Wynne ◽  
James H. Young ◽  
...  

Abstract The Seed Hull Maturity Index (SHMI) is a low cost maturity estimation method which has been shown to be correlated to yield and value per hectare using short term studies. To test the relationship of SHMI to yield and value on a long term basis, an equation was developed for deriving SHMI from 9 years of market grade information. Comparison of observed and derived SHMI values produced an R of 0.93. Among the cultivars used only Florigiant, NC6, and NC7 are either major commercial cultivars or cultivars being evaulated commercially. The data from this study confirmed that SHMI optimum values must be determined for each cultivar of interest. SHMI was shown to best estimate value per hectare. The value estimation equations for Florigiant and NC6 are given. The SHMI at which maximum value occurs is 3.0 for Florigiant and 3.1 for NC6. The SHMI at which maximum yield occurs is 2.7 for both cultivars.





2021 ◽  
Vol 253 ◽  
pp. 08002
Author(s):  
Paolo Finocchiaro ◽  
Luigi Cosentino ◽  
Quentin Ducasse ◽  
Sergio Lo Meo ◽  
Fabio Longhitano ◽  
...  

In the framework of the MICADO (Measurement and Instrumentation for Cleaning And Decommissioning Operations) European Union (EU) project, aimed at the full digitization of low and intermediate-level radioactive waste (radwaste) management, a set of 32 solid state thermal neutron detectors, named SiLiF, and 36 gamma-ray counters based on a scintillating fiber readout at each end by a silicon photomultiplier, named SciFi, have been built and characterized. MICADO project encompasses a complete active and passive characterization of the radwaste drums with neutrons and gamma rays, followed by a longer-term monitoring phase. The detectors described are suitable for the monitoring of nuclear materials and can be used around radioactive waste drums possibly containing small quantities of actinides, as well as around spent fuel casks in interim storage or during transportation. Suitable polyethylene moderators, for the SiLiF detectors, can be exploited to better shape the detector response to the expected neutron spectrum, according to Monte Carlo simulations that were performed. The SciFi detectors were thoroughly tested with a 22Na and a 137Cs gamma-ray sources. Both detectors described were tested with an intense AmBe source of neutron and gamma ray. The results are satisfactory and show a quite uniform and reproducible behavior. The next step will be the test in a real environment.



2015 ◽  
Vol 4 (2) ◽  
pp. 119-123
Author(s):  
Nicholas Chan ◽  
Pierre Wong

Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association’s radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories’ Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236 m3 resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria.



2020 ◽  
Vol 225 ◽  
pp. 05004
Author(s):  
V. Bottau ◽  
L. Tondut ◽  
P.G. Allinei ◽  
B. Perot ◽  
C. Eleon ◽  
...  

In the framework of the radioactive waste drum characterization using neutron coincidence counting, the Nuclear Measurement Laboratory of CEA Cadarache is studying plastic scintillators as an alternative to ideal but costly 3He gas proportional counters. Plastic scintillators are at least 5 times cheaper for the same detection efficiency, and in addition, they detect fast neutrons about three orders of magnitude faster than 3He detectors. However, they are sensitive to gamma rays, which implies the necessity to identify precisely gamma background sources that may affect the useful signal. This paper presents a detailed analysis of the gamma-ray spectrum of a radioactive waste drum containing glove box filters contaminated by plutonium dioxide. Gamma emissions accompanying inelastic scattering (n,n’) and (α,n) reactions that can lead to neutron-gamma coincidences parasitizing useful coincidences from plutonium spontaneous fissions are identified. Some of these parasitic gamma rays having energies up to several MeV, we plan to reject high-energy scintillator pulses with an electronics rejection threshold above 1 MeV, which should preserve the major part of useful fission neutron pulses.



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