ニッケル系金属放射性廃棄物のアークプラズマ溶融処理時におけるコバルト残存率

This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed waste. Upon approval of the permit modification, B696S rooms 1007, 1008, and 1009 will be able to store hazardous and mixed waste for up to 1 year. Furthermore, an additional drum crusher and a Waste Packaging Unit will be permitted to treat hazardous and mixed waste. RHWM generally processes LLW with no, or extremely low, concentrations of transuranics (i.e., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., {sup 90}Sr, {sup 137}Cs, {sup 3}H. Chapter 5 of the DSA documents the derivation of TSRs and develops the operational limits that protect the safety envelope defined for this facility. The DSA is applicable to the handling of radioactive waste stored and treated in the B695 Segment of the DWTF. Section 5 of the TSR, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the B695 Segment of the DWTF. A basis explanation follows each of the requirements described in Section 5.5, Specific Administrative Controls. The basis explanation does not constitute an additional requirement, but is intended as an expansion of the logic and reasoning behind development of the requirement. Programmatic Administrative Controls are addressed in Section 5.6.

Study of the nuclide inventory of operational radioactive waste for the RBMK-1500 reactor

The management of nuclear waste remains a complex issue involving scientific, environmental, regulatory, and societal dimensions. Continued research and development of innovative solutions are essential for effectively addressing the challenges associated with nuclear waste disposal. Radioactive waste is a type of hazardous waste that contains radioactive material. Radioactive waste is a result of many activities, including nuclear medicine, nuclear research, nuclear power generation, nuclear decommissioning, rare-earth mining, and nuclear weapons reprocessing. The storage and disposal of radioactive waste are regulated by government agencies to protect human health and the environment. About 96% of spent nuclear fuel in atomic plants is recycled back into uranium-based and mixed-oxide (MOX) fuels. The residual 4% is minor actinides and fission products, the latter of which are a mixture of stable and quickly decaying elements, medium-lived fission products such as strontium-90 and cesium-137, and finally seven long-lived fission products with half-lives in the hundreds of thousands to millions of years. Meanwhile, The minor actinides are heavy elements other than uranium and plutonium created by neutron capture. Their half-lives range from years to millions of years and as alpha emitters, they are particularly radiotoxic. While there are proposed – and to a much lesser extent current – uses of all those elements, commercial scale reprocessing using the PUREX process disposes of them as waste together with the fission products. The waste is subsequently converted into a glass-like ceramic for storage in a deep geological repository. The time radioactive waste must be stored depends on the type of waste and radioactive isotopes it contains. Short-term approaches to radioactive waste storage have been segregation and storage on the surface or near-surface of the earth. Burial in a deep geological repository is a favored solution for long-term storage of high-level waste, while re-use and transmutation are favored solutions for reducing the HLW inventory. Boundaries to recycling of spent nuclear fuel are regulatory and economic as well as the issue of radioactive contamination if chemical separation processes cannot achieve a very high purity. Furthermore, elements may be present in both useful and troublesome isotopes, which would require costly and energy-intensive isotope separation for their use – a currently uneconomic prospect. The amounts of radioactive waste and management approaches for most developed countries are presented and reviewed periodically as part of a joint convention of the International Atomic Energy Agency (IAEA).

This paper is a report on work in progress in support of the US Department of Energy Environmental Restoration and Waste Management (EM) Programmatic Environmental Impact Statement (PEIS). Argonne National Laboratory (ANL) has been providing technical support in the areas of waste characterization; waste treatment, storage, and disposal (TSD) facility descriptions (developed jointly with EG&G, Idaho); analysis of potential accidents at TSD facilities; and waste transportation risk assessment. Support efforts encompass the following six waste types: high-level waste; transuranic waste; low-level waste; greater-than Class-C low-level waste; low-level mixed waste; and hazardous waste. Treatment, storage, and disposal facility descriptions cover the following parameters: resource requirements, cost, staffing, capacity, by-products, and effluents. The variations in these parameters effected by the proposed alternatives are estimated. Selection of proposed initiating events, characterization of source terms, and descriptions of scenarios are covered in the accident analysis portion of the ANL work. The transportation risk assessment portion includes both off-site and on-site transportation of both radioactive and hazardous wastes for all waste management alternatives under consideration in the EM PEIS.

A Bayesian framework to update scaling factors for radioactive waste characterization

An effective scaling frequency factor method for harmonic vibrational frequencies: The factors’ transferability problem

Evaporation of High Level and Low Activity (HLW & LAW) radioactive wastes for the purposes of radionuclide separation and volume reduction has been conducted at the Savannah River and Hanford Sites for more than forty years. Additionally, the Savannah River Site (SRS) has used evaporators in preparing HLW for immobilization into a borosilicate glass matrix. The Hanford River Protection Project (RPP) is in the process of building the world’s largest radioactive waste treatment facility, Waste Treatment Plant (WTP), which will use evaporators to concentrate the liquid waste and plant recycles prior to immobilization into a borosilicate glass matrix. Radioactive waste is evaporated at each site using various evaporator designs (e.g., forced circulation, horizontal bent tube). While the equipment used to evaporate radioactive waste is relatively simple in design, the complexity in the evaporator processes in current service and in those currently in the design stages stems from the heterogeneous nature of the waste and the effects of seemingly minor components (e.g., Si) on the process. Aqueous electrolyte thermodynamic modeling and experiments have been conducted by the SRS Savannah River Technology Center (SRTC) in support of the SRS HLW and Defense Waste Processing Facility (DWPF) Evaporators and the Hanford RPP WTP. After 40 years of successful operation, accumulation of two solid phases (a nitrated aluminosilicate, Na8AL6Si6O24(NO3)2•4H2O and sodium diuranate, Na2U2O7) developed as an insoluble phase in the Savannah River Site (SRS) 2H evaporator in 1996. The aluminosilicate scale deposit caused the SRS 2-H evaporator to become completely inoperable by October 1999. Accumulation of the sodium diuranate phase on the aluminosilicate scale has caused criticality concerns. Modeling and experiments were conducted to develop a method to control the process chemistry in order to prevent the formation of aluminosilicate deposits in the future. The lessons learned from the development, design, and operation of the SRS waste treatment facilities and the currently operating 242-A Hanford HLW evaporators were applied by SRTC in support of the development and design of the Hanford WTP evaporators. Thermodynamic equilibrium modeling along with solubility and physical property experiments are being conducted to develop process control and flow sheet models. Additionally, lessons learned from the development of an advanced antifoam agent for the SRS vitrification process evaporators are being applied to the testing and development of an antifoam agent for the Hanford WTP evaporators. This paper will discuss the methodologies, results, and achievements of the SRTC evaporator development program that was conducted in support of the SRS and Hanford WTP evaporator processes. The “cross-pollination” and application of waste treatment technologies and methods between the Savannah River and Hanford Sites will be highlighted. The “cross-pollination” of technologies and methods is expected to benefit the Department of Energy’s Mission Acceleration efforts by reducing the overall cost and time for the development of the baseline waste treatment processes.

Organic waste is a type of waste that has the largest amount in Indonesia. If it is not managed properly, organic waste can cause various problems. To overcome this problem, it is necessary to make an effort to utilize organic waste which also has high economic potential. One solution to this is the use of Black Soldier Fly larvae (Hermetia Illucens) as decomposers of organic matter. The purpose of this study was to analyze the effect of the type of organic waste on the bioconversion of domestic waste using Black Soldier Fly larvae (Hermetia Illucens). This research was done using Black Soldier Fly (Hermetia Illucens) larvae of 7 days old. Two hundred larvae were used for every feeding treatment and placed in a growing cage. The feed types and feeding frequencies were varied. The feed types were three different food waste materials, were mainly composed of cucumber, banana, and canteen’s waste. The larvae were fed with 40 mg of dry weight food waste/larvae.day. The feeding frequency was varied to once per day and once in four day periods. The weight of 10% of larvae per feeding treatment was measured every four days. At the end of the experiment, the residual feed material and characteristics were measured. The level of removal of vegetable waste, fruit waste, and food waste respectively 52 %; 51 %; 55 % on the frequency of feeding once in four days. At the frequency of feeding once a day, the results were 50 %, 62 %; 67%. The C / N ratio of vegetable waste, fruit waste, and food waste residue was 8,8; 10,1; and 11,9 for the frequency of feeding once in four days, and 8,3; 9,2; and 10,6 at the frequency of feeding once a day. The moisture content in the residue of vegetable waste, fruit waste, and food waste were 92,1% respectively; 74,7%; and 77,2% at the frequency of feeding once in four days and 95,2% respectively; 72,6%; and 82,7% at the frequency of feeding once. The pH value of vegetable waste, fruit waste, and food waste is 5,54 respectively; 4,21; and 4,18 for the frequency of feeding once in four days, and 5,47 each; 5,00; and 4,16 for the frequency of feeding once a day. The suggestion for further research is that further research is needed on the effect of the acidity of the food on the mortality rate of the larvae so that the optimum pH for the growth of Black Soldier Fly (Hermetia Illucens) larvae can be found.

An effective scaling frequency factor method for scaling of harmonic vibrational frequencies: The use of redundant primitive coordinates

An effective scaling frequency factor method for scaling of harmonic vibrational frequencies: theory and preliminary application to toluene

An optical study of N-(p-n-alkyloxybenzylidene)-p-n-butyloxyanilines, nO.O4 compounds with the alkoxy chain number n = 1, 3, 6, 7, and 10 has been carried out by measuring the refractive indices using modified spectrometer and direct measurement of birefringence employing the Newton's rings method. Further, the molecular polarizability anisotropies are evaluated using Lippincott δ-function model, the molecular vibration method, Haller's extrapolation method, and scaling factor method. The molecular polarizabilities α e and α 0 are calculated using Vuk's isotropic and Neugebauer anisotropic local field models. The order parameter S is estimated by employing the molecular polarizability values determined from experimental refractive indices and density data and the polarizability anisotropy values. Further, the order parameter S is also obtained directly from the birefringence data. A comparison has been carried out among the order parameter obtained from different ways and the results are compared with the body of the data available in the literature.

Although great progress has been made in modeling the gas fluidization of Geldart B and D particles and dilute gas−solid flow by standard Eulerian approach, researchers have shown that, because of the limitation of computational resources and the formation of subgrid-scale (SGS) heterogeneous structures, Eulerian model with a suitable SGS model for constitutive law is necessary to simulate the hydrodynamics of large-scale gas-fluidized beds containing Geldart A particles. In this article, a state-of-the-art review of Eulerian modeling of Geldart A particles in gas-fluidized beds is presented. The available methods for establishing SGS models are classified into six categories, that is, empirical correlation method, scaling factor method, structure-based method, modified Syamlal and O’Brien drag correlation method, EMMS-model-based method, and correlative multiscale method. The basic ideas of those methods, as well as their advant

It is expected to establish the technology for treament of low level radioactive solid waste generated in nuclear power plants. The main problems are volume reduction and stabilization of radionuclides acceptable for final disposal. Thermal plasma technology offers advantages for such waste treatment because of the easy supply of heat at high temperature independent on chemical and physical properties of the waste.New, non-contaminated waste, such as metallic, inorganic and combustible materials, have been melted in a crucible furnace. Transferred type of a DC plasma torch with a solid electrode was used as heat source and rated up to 50kW. The main results obtained are as follows:(1) Metallic and inorganic materials can be melted and vitrified. Combustible materials can be pyrolyzed. Consequently high volume reduction rates can be attained.(2) Compressive strength of solidified products is more than twice as great as that of cement composites used for solidification of the liquid waste. Leaching rate of main components of the slag layer is in the same order of that of the high level radioactive waste glass.(3) In order to get guiding principle for design of off-gas treating system, compositions of the off-gas and properties of the dust entrained in the off-gas are clarified.From these results, technical prospects so that plasma heating technology can be applied for treatment of low level radioactive solid waste have been obtained.

Consequence analysis of a transportation accident of radioactive spent resin waste from a heavy water-cooled reactor to a the Gyeongju radioactive waste disposal facility

The THOR® fluidized bed steam reforming process has been successfully operated for more than 10 years in the United States for the treatment of low- and intermediate-level radioactive wastes generated by commercial nuclear power plants. The principle waste stream that has been treated is ion exchange resins (IER) and Dry Active Waste (DAW), but various liquids, sludges, and solid organic wastes have also been treated. The principle advantages of the THOR® process include: (a) high volume reduction on the order of 5:1 to 10:1 for IER and up to 50:1 for high plastic content DAW streams depending on the waste type and waste characteristics, (b) environmentally compliant off-gas emissions, (c) reliable conversion of wastes into mineralized products that are durable and leach-resistant, and (d) no liquid effluents for treatment of most radioactive wastes. Over the past ten years, the THOR® process has been adapted for the treatment of more complex wastes including historic defense wastes, reprocessing wastes, and other wastes associated with the fuel cycle. As part of the U.S. Department of Energy (DOE) environmental remediation activities, the THOR® dual bed steam reforming process has successfully processed: (a) Idaho National Laboratory (INL) Sodium-Bearing Waste (SBW), (b) Savannah River Tank 48 High Level Waste (HLW), (c) Hanford Low Activity Waste (LAW), and (d) Hanford Waste Treatment Plant Secondary Waste (WTP-SW) liquid slurry simulants. The THOR® process has been shown in pilot plant operations to successfully process various simulated liquid, radioactive, nitrate-containing wastes into environmentally safe, leach-resistant, solid mineralized products. These mineralized products incorporate normally soluble ions (e.g. - Na, K, Cs, Tc), sulfates, chloride salts, and fluoride salts into an alkali alumino-silicate mineral matrix that inhibits the leaching of those ions into the environment. The solid mineralized products produced by the THOR® process exhibit durability and leach resistance characteristics superior to borosilicate waste glasses. As a result of this work, a full-scale THOR® process facility is currently under construction at the DOE’s Idaho site for the treatment of SBW and a full-scale facility is in the final design stage for the DOE’s Savannah River Site for the treatment of Tank 48 high level waste. Recent work has focused on the development of new monolithic waste formulations, the extension of the THOR® process to new waste streams, and the development of modular THOR® processes for niche waste treatment applications. This paper will provide an overview of current THOR® projects and summarize the processes and outcomes of the regulatory and safety reviews that have been necessary for the THOR® process to gain acceptance in the USA.