bluuebunny/crossref_metadata_2025_split huggingface dataset:
Totemism of the Modern State: On Hans Kelsen’s Attempt to Unmask Legal and Political Fictions and Contain Political Theology
Authors: Górnisiewicz Arkadiusz 
Published: April 2020

AbstractThis paper argues that the writings of Hans Kelsen deserve more attention from those engaged in the debate on secularization and political theology. His lifelong struggle with various forms of legal‐political metaphysics is an identifiable thread in many of his writings. Kelsen’s concern with the theological‐political issues found in the theory of the state (Staatslehre) is far from being marginal. Kelsen claims that his theory aims at resolving the traditional dualism of law and state prevailing in the Staatslehre and contributes to an “uncompromising destruction of one of the most effective ideologies of legitimacy.” Kelsen maintains that the contents of this “ideology of legitimacy” derive from both political metaphysics and the deep‐seated ancient ways of thinking on nature and society. In order to illustrate this thesis, I propose calling this phenomenon “totemism of the modern state.”
Optimization of canine CD20 chimeric antigen receptor T cell manufacturing and in vitro cytotoxic activity against B‐cell lymphoma
Authors: Sakai Osamu , Igase Masaya , Mizuno Takuya 
Published: April 2020

AbstractCanine B‐cell lymphoma is one of the most common haematopoietic neoplasms in veterinary medicine, and it is considered a relevant model for human diffuse large B‐cell lymphoma. Although the standard treatment consisting of multi‐drug chemotherapy is effective in most cases, treatment is often challenging because of relapse and drug resistance. The adoptive transfer of autologous T cells genetically modified to express a CD19‐specific chimeric antigen receptor (CD19 CAR‐T cells) has been shown to be highly effective in human B‐cell malignancies. However, there is no clinically available canine CAR‐T cell therapy. We generated canine second‐generation and third‐generation CAR‐T cells by retroviral gene transduction. Optimization was performed to investigate effective viral transduction protocols and favourable culture conditions for canine CAR‐T cells. The RetroNectin‐bound virus infection method resulted in more than 70% transduction efficiency. The effect of culture conditions on the phenotype of CAR‐T cells was evaluated by the expression of surface markers. in vitro cytotoxicity assays of target cells cultured with CD20 CAR‐transduced cells demonstrated that CD20 CAR‐T cells exhibit cytotoxicity against CD20‐expressing canine B‐cell lymphoma cells and canine CD20‐transduced murine cells, whereas no effect was observed against cells that lacked canine CD20 expression. Our study established virus‐based canine CAR‐T cell generation, providing fundamental data for a better understanding of canine adoptive T‐cell therapy.
The effect of a raw vs dry diet on serum biochemical, hematologic, blood iron, B12, and folate levels in Staffordshire Bull Terriers
Authors: Anturaniemi Johanna , Zaldívar‐López Sara , Moore Robin , Kosola Mikko , Sankari Satu , Barrouin‐Melo Stella M. , Hielm‐Björkman Anna 
Published: April 2020

AbstractBackgroundTo date, very few studies have compared the effects of different types of feeding practices on canine physiology, such as feeding exclusively dry, raw, or homemade foods.ObjectivesWe aimed to report the changes in hematologic, serum biochemical, plasma folate, B12, and whole blood iron levels in dogs fed two different diets.MethodsA pilot study was developed to compare the effects of a heat‐processed high carbohydrate (HPHC) and nonprocessed high‐fat (NPHF) diet. A total of 33 client‐owned Staffordshire Bull Terriers were used; 18 had canine atopic dermatitis, seven were healthy, and eight were grouped as “borderline” dogs since they did not fulfill at least six of Favrot's criteria. The comparisons were made between the diet groups at the end visit of the diet intervention, as well as within the diet groups during the study.ResultsSignificant differences between and within the diet groups were observed, although the majority of outcomes remained within the RIs. The median time of diet intervention was 140 days. Red blood cell counts, mean cell hemoglobin concentrations, and platelet counts were significantly higher, and mean cell hemoglobin, mean cell volume, alkaline phosphatase, inorganic phosphorus, and cholesterol were significantly lower in the dogs fed the NPHF diet compared with those fed the HPHC diet after the diet trial was completed. In addition, folate, B12, and iron decreased significantly in the NPHF diet group.ConclusionsThis pilot study indicated that diet had an impact on blood values, although most remained within RIs, pointing out the need for further studies.
Cementation Process for the Conditioning of Liquid Radioactive Wastes Produced During Fuel Element Reprocessing
Authors: Lippolis G. , Petagna E. , Bitonte G. , Pastore C. , Ragazzo G. , Tortorelli P. 
Published: April 2020

Abstract
In the past years many studies have been carried out in ITREC Plant, located in ENEA - Trisaia Research Centre, in the field of nuclear fuel reprocessing. During these activities high and low level liquid wastes were produced and stored in a special area of tanks, named Waste-1.
A specific plant, SIRTE (Integrated System for Effluents Raising and Treatment) was built, in order to condition the liquid wastes, composed of fission products, beta and gamma emitters. This plant is based on the process of cementation.
In this work, the characteristics of the plant, the phases of conditioning process and the radiological monitoring program, performed inside the plant, during the campaigns of cementation, are shown.
Proposal for Internationally Standardised Cost Item Definitions for the Decommissioning of Nuclear Installations
Authors: Teunckens Lucien , Pflugrad Kurt , Chan-Sands Candace , Lazo Eduard 
Published: April 2020

Abstract
Various international decommissioning projects have shown that there are substantial variations in cost estimates for individual installations. Studies to understand the reasons for these differences have been somewhat hampered by the fact that different types of cost estimation methods are used, having different data requirements. Although some uncertainty is inevitable in any costing method, an understanding of the costing methods used in particular projects is useful to avoid key uncertainties. Difficulties of understanding can be encountered and invalid conclusions drawn in making cost comparisons without regard to the context in which the various cost estimates were made.
The above-mentioned difficulties are partly due to the lack of a standardised or generally agreed-upon costing method that includes well structured and defined cost items and an established estimation method. Such a structure and method would be useful not only for project cost comparisons, but would also be a tool for a more effective cost management.
The OECD/Nuclear Energy Agency (NEA), the International Atomic Energy Agency (IAEA), and the European Commission (EC) have ongoing activities addressing various aspects of decommissioning and decommissioning costs. Based on these concurrent activities and common objectives, and on the advantages of standardised cost item definitions, the three organisations agreed to jointly prepare and to publish a standardised list of cost items and related cost definitions, for decommissioning projects. The work was carried out by Belgoprocess (Belgium) in the framework of a shared-cost contract with the European Commission (Nuclear Fission Safety Programme 1994–1998). This paper presents the results of the co-operative work.
Plasma Treatment of Radioactive Waste in Shaft Furnace
Authors: Polkanov M. A. , Savkin A. Eu. , Dmitriev S. A. , Lifanov F. A. , Popkov V. N. , Gorbunov V. A. , Spirin N. A. , Oskolkov Yu. A. , Shvetsov S. Yu. , Burov M. Yu. , Vitik N. V. 
Published: April 2020

Abstract
Moscow SIA RADON has developed and tested an experimental plant for treatment of radioactive waste of the mixed type including up to 40 wt. % of incombustible components with the capacity from 50 to 80 kg/h on the base of the shaft furnace with plasma heat source. Heating furnace was provided due to the arc DC plasma torch with electric capacity from 60 to 150 kW, designed at RADON. The expenses of the electric power for plasma torch were 0.5 up to 1.5 kWh/1 kg of waste depending on their composition. Pyrolytic gas with calorific value up to 4.5–5.5 MJ/kg at an output of the furnace was received, which burning provided a necessary temperature mode in the afterburner. In the shaft furnace the mode impeding radionuclides loss with off-gases has been realized. The ablation of 137Cs from the furnace did not exceed 12%, 60Co – 2.5% and trans-uranium elements – 1% due to the shaft operation mode chosen. The treatment of radioactive waste without fluxing additives has been carried out, and the slag compound with high chemical durability has been obtained.
Self-Paid Back Technologies of Clearing of Territories Contaminated With Radionuclides
Authors: Sharavarau H. , Basharin A. , Sharovarova M. , Drougatchenok M. , Bayle E. , Guiroy J. , Ardisson J. 
Published: April 2020

Abstract
After the explosion of the Chernobyl Nuclear Power Plant a great amount of radioactive substance was thrown out of the wrecked reactor into the atmosphere. The fall-out covered the territory of Belarus in a few big spots. The total area of the territory of Belarus contaminated with radionuclides amounts to 46.5 thousand km2. It is more than 20% of the whole territory. After the Chernobyl accident Belarus has become the zone of the ecological disaster.
Chernobyl NPP Decommissioning and “Shelter” Object Transformation: Problems of Activity Coordination
Authors: Semenova Iryna Y. , Steinberg Nikolay A. 
Published: April 2020

Abstract
The shutdown of the last Chernobyl NPP (ChNPP) unit essentially changes situation at the site. The plant terminates the activity as the electricity producer and starts decommissioning of the nuclear installations, located at the site. At the same time an activity connected with transformation of the “Shelter” object (the object has been erected to cover unit 4 of ChNPP destroyed by the accident at the April 26, 1986) in an ecologically safe system continues at ChNPP site. There are a large amount of scientific, engineering, economical and political issues connected to the both activities have been arisen in the past and should be resolved in the years to come.
Scope and the complexities of the tasks must be performed at the site, have no analogs in the world. The nuclear world has accumulated experience of different nuclear installations decommissioning, including NPP units, but still never taken out of service multiunit NPP in a full structure, including the unit, destroyed by the accident. Chernobyl site is unique because of 1986 accident consequences. The “Shelter” object is even more unique. The clear safety regulations for ChNPP decommissioning and the “Shelter” object transformation in an ecologically safe system are missed till now. The attempts to apply the regulations destined for “ordinary” nuclear installations in an “ordinary” surrounding environment brings up amount of issues. It is obvious that particular conditions of surrounding area, the exclusion zone, should be taken into account. The principle of “reasonable sufficiency” should be implemented to reach the safety goals of the ChNPP decommissioning and the “Shelter” object transformation without excessive financial loses and doze commitment.
Some important issues still remain unsolved: long-lived low and middle level solid radwaste (SRW) storage and storage of high-level SRW; damaged spent fuel assemblies management; polluted soil management. There is no solution on radioactive by-products management collected by the cooling lake of ChNPP in the consequences of the accident.
Large amount of radwaste and spent fuel collected at ChNPP site brings up the question about possibility and expediency of radwaste management infrastructure using which is created at ChNPP site in accordance to the National Radwaste Management Program. Obviously this question requires serious comprehensive analysis to make final decision.
Some of issues connected to peculiarities of ChNPP decommissioning and the “Shelter” object transformations in ecologically safe system (including coordination of both activities) are discussed in the presentation.
Simulation of Radionuclide Release and Subsurface Transport for LILW New Romanian Repository
Authors: Didita Liana , Ilie Petre , Pavelescu Margarit , Danchiv Alexandru , Martac George 
Published: April 2020

Abstract
This paper presents the main stages covered in development of the safety assessment methodology for near surface Romanian repository. It also describes the modeling approaches and assumptions used in source term modeling as well as the radionuclides transport through the unsaturated and saturated zones.
In the paper, the repository performance is assessed only by the normal evolution scenario and the beginning of the institutional control period. Transport modeling through unsaturated zone emphasizes its behaviour as a natural barrier in radionuclide migration’s way. Only a brief discussion of radionuclide transport through the saturated zone is given in this paper. The discussion is related first to the model’s characteristics, followed by the presentation of the results.
Dismantling Policy and Practice
Authors: Van Rentergem Th. 
Published: April 2020

Abstract
A distinction has to be made between:
• The installations still in profitable operation, such as the nuclear power plants, plants of BELGONUCLEAIRE, FBFC, “CILVA”, waste storage buildings. Hereafter, I will only speak of the most important ones, namely the nuclear power plants.
• The older installations, which have been closed or which are to be closed soon and which have never been and will never be in a profitable operation. These installations are the old Eurochemic-plant, the old waste department of the SCK•CEN, the reactors and laboratories of the SCK•CEN (BR3, BR2, …, LHMA, …), the Institute of Radio-elements in Fleurus.
Services to Nuclear Industry
Authors: Vandorpe M. 
Published: April 2020

Abstract
Services to the nuclear industry started at the very beginning of the nuclear industry with the construction of the first commercial units. Based on the knowledge developed in laboratories, small units were constructed and gradually extended to the large plants actually in service.
Over the past few years, reverse operations have been undertaken with the decommissioning of and the green-field operations for the oldest units.
At all stages of this work as well as during the main outage operations, external firms have been involved. Progressively these companies have built up specific knowledge including both the technical requirements identical to those of non-nuclear interventions (mechanical, electrical, engineering…) and the more nuclear-related ones (quality and safety requirements, radwaste management, radiological aspects, alara principles…).
The Decreasing Ways of Contaminated Underground Water Volume in Uranium Mining and Milling Region
Authors: Isayeva Natalya 
Published: April 2020

Abstract
Ukrainian uranium ore mining and milling facilities are located in the tight populated areas on the valuable agricultural lands of Ukraine. The almost 50th years’ activity of these enterprises has caused the radioactive contamination of the environment. The most dangerous facilities happened to be those ones which contaminate the entrails for a long time, namely: tailings which were discharged with the uranium ore uranium mill and former uranium in-situ leaching sites which are now decommissioned and left without relevant environmental protection measures. This paper considers two uranium facilities, which impact in a similar way on such an environmental entity as underground water: the tailings and in-situ leaching site located in Dnipropetrovsk region.
Operational Experience of TN 24 Dual Purpose Spent Fuel Storage Casks at the DOEL Nuclear Power Plants in Belgium
Authors: Baroux C. , Detrilleaux M. , Demazy G. 
Published: April 2020

Abstract
Spent nuclear fuel has been stored at the DOEL power station in Belgium in dual-purpose metal casks since 1995. The casks were procured from TRANSNUCLEAIRE by SYNATOM to meet the operational demands for on-site dry storage solutions for fuel arising from the four PWR reactors at DOEL. The TN 24 type of cask was chosen and a range of different cask types were developed.
The initial requirement was for dual purpose cask to contain fuel from the DOEL units 3 and 4, these having similar fuel types but different lengths, and thus two new members of the TN 24 family were developed; the TN 24 D and TN 24 XL with capacities of 28 and 24 SFA’s. These casks were licensed as B(U) fissile packagings with approval certificates granted by the French and validated by the Belgium competent authorities for the transport configurations. Both cask designs were also analyzed by TRANSNUCLEAIRE in their storage configurations to ensure that the criteria for safe interim storage could be met.
Since 1995, a total of 18 TN 24 D and TN 24 XL casks have been loaded with spent fuel assemblies with an average burn-up of 40,000 MWd/tU. SYNATOM subsequently decided to purchase further casks for DOEL 3 and 4 fuels with higher enrichments, higher burn-ups and shorter cooling times. TRANSNUCLEAIRE developed the TN 24 DH and TN 24 XLH casks within the similar envelope size and weight limits. The increase in performance was achieved by an in-depth optimization of each design in terms of radiation shielding, heat transfer and criticality safety. This paper shows how this optimization process was undertaken for the TN 24 DH and TN 24 XLH casks, 16 of which have been ordered by SYNATOM. DOEL 1 and 2 units use much shorter PWR fuel and it was decided to ship the fuel to unit 3 with an internal transfer cask because the handling limitations in the DOEL 1 and 2 pool prohibited the loading of a high capacity dual purpose transport/storage cask. The TN 24 SH cask was subsequently designed for DOEL 1 and 2 PWR fuel with a capacity of 37 assemblies and nine of there casks have been ordered by SYNATOM.
The casks are fitted with monitoring devices to detect any change in the performance of the double metal O ring closure system and none of the casks has shown any deterioration in leaktightness. This paper examines the operation experience of loading and storing more than 30 TN 24 dual purpose casks and compares the performance with design expectations.
Experience of Clean-Up Activities and Feedback to Future D&D Projects: Japan Power Demonstration Reactor Decommissioning Project
Authors: Yanagihara Satoshi , Tachibana Mitsuo , Shimada Taro , Sukegawa Takenori , Shiraishi Kunio 
Published: April 2020

Abstract
In the Japan Power Demonstration Reactor (JPDR) decommissioning project, the procedure for clean-up activities was specially studied for harmonization with radioactive waste treatment policy in Japan; it consisted of several components such as survey of the facility operational history, radiological characterization of building surfaces, decontamination and final survey of radioactivities. After confirming that there was no significant radioactivity in the facilities in the final step of the procedure, buildings were demolished in consideration of treatment of wastes as non-radioactive materials. The JPDR decommissioning project was completed by March 1996 with no serious problems, which showed that the procedure was rational, and that the experiences are useful for planning of future decommissioning activities. The dismantling and clean-up activities were reviewed, and the experiences are excepted to contribute to establishing standard and regulatory systems on decommissioning nuclear facilities.
Temperature Criterion Related to Clay Based Backfill Materials in the Framework of a Geological Repository of Heat Producing Radioactive Waste (HLW)
Authors: Bel Johan , Bernier Fréderic 
Published: April 2020

Abstract
The objective of this paper is to define a criterion for the maximum temperature allowed within clay based backfill materials, used as engineered barriers, in the framework of a geological repository of heat emitting radioactive waste. This criterion applies to all candidate geological formations in Belgium (non-indurated clay).
According to the current Belgian reference repository for vitrified High Level Waste (HLW), waste packages will be disposed in deep geological clay formations after a cooling period of about 50 years in surface storage facilities.
The heat release of this waste has a important impact on the design of the different components of the disposal system. The temperature increase and the possible effects of this increase will have to be considered on different locations (e.g. disposal galleries, backfill, lining, host rock, aquifer, and biosphere). In this paper, we will focus mainly on the temperature increase in the backfill material of the galleries.
In the past the temperature in the host rock (Boom Clay) was limited to 100°C. Consequently, higher temperatures (above 100°C) were allowed in the components between the waste and the host rock. During the preparation of the in situ demonstration project PRACLAY, a new more stringent criterion for the limitation of the temperature in the backfill has been proposed, namely the limitation of the temperature in the backfill to 100°C.
The different scientific and technical reasons for the use of this lower temperature design criterion are described in this paper. Phenomena like steam generation, mineral transformations and thermally induced, coupled effects can be reduced or avoided at lower temperatures. Another important advantage is the reduction of the corrosion rate of metal components (e.g. overpack). Finally, problems of a more technical nature (difficulty of characterization of materials, uncertainty in modeling and problems with instrumentations) can also be avoided by the use of this new criterion.
Thermal calculations point out that this new criterion can be met by respecting a cooling time, for the present repository design of vitrified HLW, of 60 years instead of 50 years.
We can conclude that the application of this lower temperature criterion provides better predictability of coupled effects and increases the performance, lifetime and robustness of the different barriers of the repository and of the disposal system as a whole.
The Recovery of Shallow Land Burial Waste
Authors: Vassallo Gary , Bielli Giuseppe , Bertelli Sergio , Marcon Gabriel , Giuffrida Daniele , Rouvière Jacques , Bertet Pierre 
Published: April 2020

Abstract
The JRC must recondition various radioactive wastes that were placed in a shallow land burial site during the 1960s and 70s. One such waste type at the Ispra Site are the so-called Roman pits, 7 m high columnar concrete containers in which activated metals were deposited and immobilised with cement. JRC-Ispra has fifteen such waste forms that must be recovered, characterised and reconditioned. This paper discusses the background to the Roman pits, the development of a validation procedure for demonstrating the safe recovery of a pit, and finally, the procedure’s execution.