scholarly journals Radiation Protection Calculations for the New Radioactive Waste Interim Storage Facility of NCSR “Demokritos"

2019 ◽  
Vol 21 ◽  
pp. 141
Author(s):  
I. Karachristou ◽  
St. Chouvardas ◽  
G. Terzoudi ◽  
A. Savidou

The present study concerns the determination of the maximum acceptable contact dose rate per radioac- tive waste package for safekeeping at the New Radioactive Waste Interim Storage (NRWIS) of the National Centre for Scientific Research “Demokritos” (NCSR “D”). The NRWIS facility is used for temporary storage of spent/ orphan sealed sources, devices like lightning rods and primary radioactive waste. The contact dose rate per package is determined in a level that even in case the highest radiation background is built up in- side the storage facility, the doses to the workers will not exceed the maximum permissible doses. The total dose that a worker receives inside the facility should not exceed one half of the annual occupational dose constraint of 6 mSv. Furthermore in cases of the highest radiation background inside the facility, shielding calculations are performed.


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).



2021 ◽  
Author(s):  
Georgeta Radulescu ◽  
Kaushik Banerjee ◽  
Douglas Peplow ◽  
Thomas Miller


Author(s):  
Jeroen Welbergen ◽  
Leo van Velzen

All radioactive waste in the Netherlands is collected by COVRA (acronym for Central Organisation for Radioactive Waste) that operates a facility for treatment of waste including interim storage buildings for HLW, LILW and TENORM (Calcinate and U3O8). Like many other waste management organisations, COVRA developed and adopted different waste storage strategies for different types of waste. The basis of all strategies is Isolation, Control and Surveillance (ICS), a principle aimed at minimization of dose to operators and the public alike. The stacking of waste in the storage buildings directly follows from this principle. To minimize radiation exposure of employees, waste is stacked in blocks. In these block the packages with low dose rates are placed on the outside and are shielding packages with higher dose rates and neutron sources inside. The packages with the lowest dose rate are stacked against the outer walls to minimize radiation into the environment. In 2004, a novel Non-Destructive Assay (NDA) method was used to validate the applied waste storage strategies in terms of spatial dose rate distribution. With this method measurements were performed in one of the interim storage modules for LILW. The dose rate at a height of 6m, mainly responsible for the sky-shine at the site boundary, was somewhat higher then expected. Based on the experience and feedback, the NDA method was developed further, into the present INDSS-R (acronym for INDoor Survey System – Radiation) method. This new method was put to the test in 2006 with a second series of spatial radiological measurements. The main aim was now to verify the reproducibility of the method. In 2008, a third series of measurements was carried out and the following data was collected: • dose rate (using a pressurized ionisation chamber) • nuclide depended gamma photon flux (by means of a 3*3″ NaI detector ) • thermal neutron flux measurements (by means of LiI(Eu) detector) The results of the third serial of spatial radiological and thermal neutron flux measurements will be presented and compared to the 2004 and 2006 data on the operational dose for operators and for the public.





Sensors ◽  
2021 ◽  
Vol 21 (8) ◽  
pp. 2630
Author(s):  
Luigi Cosentino ◽  
Quentin Ducasse ◽  
Martina Giuffrida ◽  
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 management, a set of 32 solid state thermal neutron detectors named SiLiF has been built and characterized. MICADO encompasses a complete active and passive characterization of the radwaste drums with neutrons and gamma rays, followed by a longer-term monitoring phase. The SiLiF detectors 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 can be exploited to better shape the detector response to the expected neutron spectrum, according to Monte Carlo simulations that were performed. These detectors were extensively tested with an AmBe neutron source, and the results show a quite uniform and reproducible behavior.



1988 ◽  
Vol 127 ◽  
Author(s):  
D. Broc ◽  
F. Plas ◽  
J. C. Robinet

ABSTRACTThe safety of vitrified radioactive waste disposal in granite is based on the concept of multiple barriers, which include an engineered clay barrier placed between the waste package and the granite. The mechanical properties of the swelling clays used were studied with a view to practical application for storage facility dimensioning. This involved a macroscopic examination of the clays swelling capacities (for sealing of storage boreholes) and fracture criteria (mechanical stability).



1991 ◽  
Vol 93 (3) ◽  
pp. 611-635 ◽  
Author(s):  
Richard W. Stoffle ◽  
Michael W. Traugott ◽  
John V. Stone ◽  
Paula D. McIntyre ◽  
Florence V. Jensen ◽  
...  


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