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At least 883 records · Page 49
All sourcesNASA NTRSDOE OSTI
DOE OSTI2016

Solidification technology for organic liquid waste combined with solid materials from Cernavoda NPP, Romania - 16453

Canadian Deuterium Uranium (CANDU{sup R}) reactor designs were initially developed in the late 1950's and 1960's by the Atomic Energy of Canada Limited (AECL) in partnership with Ontario Power Generation. CANDU{sup R} 6 reactors are Pressurized Heavy Water Reactors (PHWRs), with an integrated containment system and are designed as either multi or single unit systems. Two single CANDU 6 systems are currently operating at Cernavoda with an additional two units expected to be brought online in the near future. The radioactive waste produced by the plant is currently stored in a waste interim storage facility located on-site. The main sources of radioactive waste in a CANDU plant are: - Primary Heat Transport (PHT) systems, - Moderator systems, - Other sources of radionuclides. The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. During the operation of the Cernavoda NPP, a series of waste streams have been generated for waste treatment purposes. One important waste stream is the combination of solid materials and liquid organic waste, creating flammable solids. Flammable solids represent solid materials, such as cloth, plastic, contaminated with oil containing gamma nuclides and H-3 from maintenance activities. This paper explores a method to solve the problem of liquid residues on solid materials by the application of absorbent materials. The existence of liquid residues on solid materials is a common problem at nuclear power stations globally. The primary issue centers on an effective method of eliminating the liquid to allow for the final acceptance and disposal of the solid waste by regulators. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2024

Ceramic–Metal (Cermet) Composites: A Review of Key Properties and Synthesis Methods Focused on Nuclear Waste Immobilization

Here this paper reviews key properties, applications, and examples of ceramic-metal composites (cermets), and metal matrix composites (MMC) with emphasis on their applicability as waste forms for immobilizing nuclear waste. While the literature is mature for vitrified and cementitious radioactive waste forms, cermet materials have not received adequate attention as potential candidates for immobilizing nuclear waste. To promulgate this effort, this review connects cermet and MMC design, such as hardened tools, with the chemistry of radioactive waste streams. A discussion on certification and qualification standards for cermet waste forms, literature gaps, and “how-to” sections on cermet processing techniques. Key parameters discussed include thermal conductivity, chemical durability, and waste loading, as well as examples for metal-containing waste forms. As cermet waste forms gain momentum within the community, this review paper aims ensure the end-of-life nuclear fuel cycle is addressed from a materials and waste disposition perspective.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗
DOE OSTI2013

An integrated approach to geological disposal of UK wastes containing carbon-14

Carbon-14 is a key radionuclide in the assessment of the safety of a geological disposal facility for radioactive waste because of the calculated assessment of the radiological consequences of gaseous carbon-14 bearing species [i]. It may be that such calculations are based on overly conservative assumptions and that better understanding could lead to considerably reduced assessment of the radiological consequences from these wastes. Alternatively, it may be possible to mitigate the impact of these wastes through alternative treatment, packaging or design options. The Radioactive Waste Management Directorate of the UK's Nuclear Decommissioning Authority (NDA RWMD) has established an integrated project team in which the partners are working together to develop a holistic approach to carbon-14 management in the disposal system [ii]. For a waste stream containing carbon-14 to be an issue: There must be a significant inventory of carbon-14 in the waste stream; and That waste stream has to generate carbon-14 bearing gas; and a bulk gas phase has to entrain the carbon-14 bearing gas: and these gases must migrate through the engineered barriers in significant quantities; and these gases must migrate through the overlying geological environment (either as a distinct gas phase or as dissolved gas); and these gases must interact with materials in the biosphere (i.e. plants) in a manner that leads to significant doses and risks to exposed groups or potentially exposed groups. The project team has developed and used this 'and' approach to structure and prioritise the technical work and break the problem down in a manageable way. We have also used it to develop our approach to considering alternative treatment, packaging and design options. For example, it may be possible to pre-treat some wastes to remove some of the inventory or to segregate other wastes so that they are removed from any bulk gas phase which might facilitate migration through the geosphere. Initially, the project team has undertaken a six month programme of work to examine the current understanding of these aspects and has captured this in the Phase 1 report [ii], in a modelling basis spreadsheet and in scoping assessments, which help us better understand the potential significance of carbon-14. Using the current modelling basis, but ignoring any potential benefits from the geosphere in retarding or preventing gas from reaching the surface, the calculated release of carbon- 14 is dominated by: corrosion of irradiated reactive metals (in the operational and early post-closure time frame); corrosion of irradiated stainless steel and leaching of irradiated graphite (in the longer term). The Phase 1 work has shown that there is considerable scope for reducing the calculated radiological consequence for these wastes and a roadmap has been developed for a second Phase of work. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Contaminant Leach Testing of Hanford Tank 241-C-104 Residual Waste

Leach testing of Tank C-104 residual waste was completed using batch and column experiments. Tank C-104 residual waste contains exceptionally high concentrations of uranium (i.e., as high as 115 mg/g or 11.5 wt.%). This study was conducted to provide data to develop contaminant release models for Tank C-104 residual waste and Tank C-104 residual waste that has been treated with lime to transform uranium in the waste to a highly insoluble calcium uranate (CaUO4) or similar phase. Three column leaching cases were investigated. In the first case, C-104 residual waste was leached with deionized water. In the second case, crushed grout was added to the column so that deionized water contacted the grout prior to contacting the waste. In the third case, lime was mixed in with the grout. Results of the column experiments demonstrate that addition of lime dramatically reduces the leachability of uranium from Tank C-104 residual waste. Initial indications suggest that CaUO4 or a similar highly insoluble calcium rich uranium phase forms as a result of the lime addition. Additional work is needed to definitively identify the uranium phases that occur in the as received waste and the waste after the lime treatment.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Fiscal Year 2018 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada

The U.S. Department of Energy Standard Disposal Authorization Statement and Tank Closure Documentation (DOE-STD-5002-2017) requires preparation of an Annual Summary Report comparing low-level radioactive waste disposal facilities operations with the Disposal Authorization Statement (DAS) and its supporting technical documents including the performance assessment (PA) and the composite analysis (CA). The fiscal year (FY) 2018 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) was prepared by reviewing planned and discovered changes, waste receipts, monitoring results, research and development (R&D) results, and the status of DAS conditions and issues to assess the validity of the DASs, PAs, and CAs. The Area 3 RWMS was placed in stand-by in 2006 and remained inactive in FY 2018. Resumption of waste disposal operations is planned for FY 2019. No proposed actions, new information, or discoveries affecting the Area 3 RWMS were identified in FY 2018. No significant changes have occurred since preparation of the most recent special analysis, which indicates a continuing reasonable expectation of meeting the PA performance objectives and measures, and the CA dose constraint in DOE O 435.1, “Radioactive Waste Management.” No changes were made to documents supporting the Radioactive Waste Management Basis (RWMB) including the PA, CA, DAS, waste acceptance criteria (WAC), closure plan, monitoring plan, or maintenance plan. Monitoring results for the most recent year with available data, calendar year (CY) 2017, indicate no changes to long-term trends and no results inconsistent with expected performance. R&D results for the Area 3 RWMS Drainage Lysimeter Facility continue to be consistent with the conceptual site model (CSM). All Area 3 RWMS DAS conditions and secondary issues were closed in 2002. The Area 5 RWMS continued disposal operations within the Northern Expansion Area in FY 2018. Eighty-six changes involving proposed actions, new information, or discoveries affecting the Area 5 RWMS PA and CA were screened during FY 2018 in the Unreviewed disposal question (UDQ) process. Twenty-two changes required UDQ evaluations and two changes resulted in unreviewed composite analysis question evaluations. None of the proposed actions, new information, or discoveries had significant impacts on the PAs or CAs. All of the planned changes were implemented. No special analyses were performed, and no changes were made to documents supporting the RWMB including the PA, CA, DAS, WAC, closure plan, monitoring plan, or maintenance plan. Planning continued and construction commenced on development of the Western Expansion Area within the Radioactive Waste Management Complex. All Area 5 RWMS DAS conditions and secondary issues were closed in 2002. The cumulative effects of changes occurring since preparation of the Area 5 RWMS PA and CA were assessed with the current baseline PA/CA model. Model results indicate that there is a reasonable expectation that the PA performance objectives and measures, and the CA dose constraint in DOE O 435.1, “Radioactive Waste Management,” can be met. No PA or CA mean result exceeds 50% of its performance objective. Monitoring results and R&D results continue to be consistent with the CSM. Monitoring results for CY 2017 indicate no changes to long-term trends and no results inconsistent with expected performance. R&D results for the Area 5 RWMS Weighing Lysimeter Facility continue to be consistent with the CSM. The FY 2018 review of Area 3 RWMS and Area 5 RWMS disposal operations supports the following conclusions: The Area 3 and Area 5 RWMS PA and associated CA assumptions and conclusions remain valid based on consideration of all changes identified or planned; The reasonable expectation that the Area 3 and Area 5 RWMSs will meet the performance objectives identified in DOE O 435.1, “Radioactive Waste Management”, remains valid; and The DAS, based on interpretation of the data collected, monitoring results, and other information, continues to be adequate.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

Vitrification of IFR and MSBR halide salt reprocessing wastes

Both of the genuinely sustainable (breeder) nuclear fuel cycles (IFR - Integral Fast Reactor - and MSBR - Molten Salt Breeder Reactor -) studied by the USA's national laboratories would generate high level reprocessing waste (HLRW) streams consisting of a relatively small amount ( about 4 mole %) of fission product halide (chloride or fluoride) salts in a matrix comprised primarily (about 95 mole %) of non radioactive alkali metal halide salts. Because leach resistant glasses cannot accommodate much of any of the halides, most of the treatment scenarios previously envisioned for such HLRW have assumed a monolithic waste form comprised of a synthetic analog of an insoluble crystalline halide mineral. In practice, this translates to making a 'substituted' sodalite ('Ceramic Waste Form') of the IFR's chloride salt-based wastes and fluoroapatite of the MSBR's fluoride salt-based wastes. This paper discusses my experimental studies of an alternative waste management scenario for both fuel cycles that would separate/recycle the waste's halide and immobilize everything else in iron phosphate (Fe-P) glass. It will describe both how the work was done and what its results indicate about how a treatment process for both of those wastes should be implemented (fluoride and chloride behave differently). In either case, this scenario's primary advantages include much higher waste loadings, much lower overall cost, and the generation of a product (glass) that is more consistent with current waste management practices. (author)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

A French Industrial Management Plan for Very Low Level Radioactive Wastes (VLLW) at the CIRES Facility - 17012

Since 2003, very-low-level waste has been disposed of at the Andra CIRES disposal facility, the first disposal facility in the world for this type. It is now the main route in terms of volumes for the management of French radioactive waste. The 2015 national inventory has identified 1.1 million m{sup 3} of VLLW to be produced until 2030. Several waste management scenarios were then analyzed, including issues associated with the flow reduction of the waste to be stored. The key avenues to reduce the volumes of waste, technical and economic viability of which still needing to be challenged, are at this stage: - Favor the reuse of large amounts of metallic VLLW to be produced within the next decade. - To service the recycling of metals, different opportunities for reuse should be considered -including within the non-nuclear sector. - 30% to 50% of VLLW produced in the so-called 'nuclear waste' areas probably have zero or non-detectable radioactivity levels and questions about the introduction of a clearance level. - A disposal route based on a concept derived from waste storage facility for non-nuclear and non-hazardous wastes could be an alternative to the clearance level for the least active inert waste. Therefore volumetric optimizations appear possible, even if the waste management costs will be higher than the current route. Furthermore, efficiency gains and progresses in operating modes would increase the technical capacity of the CIRES of about 250 000 m{sup 3}. In all cases studied, it appears essential to create around 2030 a new VLLW disposal facility, particularly for the dismantling of the current fleet of reactors. According to the proposed optimizations, the necessary capacity for a second VLLW disposal facility would range between 600 000 m{sup 3} and 1.2 million m{sup 3}. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Separable Organic Evaluation: Waste Feed Delivery Impacts - 17563

The potential for separable organic materials to separate out from Hanford tank waste requires consideration for future Waste Feed Delivery operations. Separable organic materials are organic compounds of very limited solubility in bulk waste that can form a separate phase or layer. If the organic materials bound to waste separates during mixing and transfer operations, the feed batch would be disqualified under the Hanford Tank Waste Treatment and Immobilization Plant (WTP) waste acceptance criteria for 'no visible immiscible layer.' Sample data and process history were used to identify tanks with the potential to contain separable organic materials. Centrifuge testing was performed on available archived tank samples and on waste simulants developed to mimic characteristics of the archived tank samples. A separable layer formed during centrifuge testing of archived samples 241-C-204, 241-SY-102, and for all developed simulants tested. Due to the formation of a separable organic layer during the centrifugation studies, an impact assessment was performed. This impact assessment identified forty-four potential tanks of concern regarding the release of organic material bound to solids during waste disturbing activities. A Hanford Tank Waste Operations Simulator model run was modified to trace the origin of each batch to the WTP. The outputs of the model run indicated that a separable organic layer would form during High Level Waste Feed Delivery operations and would cascade to all tanks containing or receiving significant amounts of organic solvents/diluents. Hence, there is a potential for a ripple effect across the feed batches. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Filtration Improvements in Support of Increased Salt Waste Processing Throughput at the Savannah River Site - 16173

Crossflow Filtration is currently used at the U.S. Department of Energy (DOE) Savannah River Site (SRS) for the removal of actinides, strontium and sludge solids from the high-level salt waste stored in underground tanks. At SRS, crossflow filtration is deployed in the Actinide Removal Process (ARP). Salt waste is transferred from an underground waste tank to one of two strike tanks where it is struck with Monosodium Titanate (MST), which adsorbs uranium, plutonium and strontium. The MST laden salt waste is then transferred to the ARP filtration facility, which contains the crossflow filter. The filtrate, which is called Clarified Salt Solution (CSS), is sent to a downstream facility for cesium removal, while the MST and sludge solids are concentrated at the filtration facility and eventually sent to the Defense Waste Processing Facility (DWPF) for vitrification. ARP and the downstream cesium removal facility, the Modular Caustic Side Solvent Extraction Unit (MCU), were both developed as an interim salt waste processing technology and as smaller scale radioactive demonstration plants for the Salt Waste Processing Facility (SWPF), which is currently under construction. Since the beginning of ARP in 2008, there have been challenges with achieving desired filtration rates through the crossflow filter system. Historically the crossflow filter system has been the flow limiter in salt waste processing and many changes have been made and are planned to achieve desired throughput, especially as MCU increases its processing capacity. Some of these changes include the design of a new crossflow filter, the implementation of a new process chemistry flowsheet and several operational changes. The modifications to the ARP crossflow filter have helped contribute to periods of record throughput in salt waste processing in FY 2015. This paper will discuss the technical challenges and system limitations of retrofitting an older facility as well as past, present and future modifications to the ARP filtration process in order to achieve salt waste processing goals at SRS. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Working in partnership with the UK nuclear industry to package waste - 16263

Radioactive Waste Management (RWM) is a wholly owned subsidiary of the Nuclear Decommissioning Authority (NDA), which is responsible for managing the effective clean-up of the UK's nuclear legacy. RWM is responsible for delivering a geological disposal facility and providing radioactive waste management solutions. To this end, RWM provides advice to waste owners to help them retrieve, condition and package waste now in ways that make them suitable for disposal later. To facilitate planning decisions and hazard reduction, RWM operates the Disposability Assessment process. This is used to provide advice to waste producing organisations on approaches to waste packaging and interim storage of packaged wastes. This advice is intended to ensure compatibility with future geological disposal requirements, as far as this is possible in advance of the availability of Waste Acceptance Criteria for a Geological Disposal Facility (GDF). As such, it is an enabler for early hazard reduction on UK nuclear sites through the facilitation of packaging. This paper explains how RWM is working with waste owners through the Disposability Assessment process to deliver optimised waste packaging solutions through proactive and early engagement. This includes specific examples of how the process has been used in a flexible way to contribute to accelerated and sustainable hazard reduction at UK sites using a partnership approach. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Benefits of a Full Waste Cost Recovery Program - 16322

A full waste cost recovery program has been established at the INL in order to fund disposition of all newly-generated hazardous, radioactive, and mixed waste at the INL. Significant improvements have resulted from implementation of this program at the INL, and it is anticipated that others could benefit from using a similar approach. The INL Waste Management Program (WMP) administers two site-wide service centers that collect revenue from programs and projects in order to pay waste disposition costs. These service centers are administered separately due to their unique scope and functions. The combination of these service centers provides the INL with a fully functional cost recovery program for all newly generated waste. This cost recovery program ensures that funding is available for disposition of all waste types and that waste costs are paid for by the generating programs or facilities. The implementation of these service centers in Fiscal Year 2014 has resulting in several significant improvements in waste disposition, including a substantial increase in awareness and emphasis on waste minimization and segregation. The service centers have virtually eliminated funding shortfalls from projects that end and have not budgeted for dispositioning waste. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Integrated Waste Feed Qualification Program for Direct LAW Feed to WTP - 16421

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a one-of-a-kind facility being designed and constructed for DOE by Bechtel National, Inc. (BNI) and principal subcontractor URS, to process and vitrify radioactive waste stored in underground tanks at the Hanford Site. The Tank Operations Contractor (TOC), Washington River Protection Solutions (WRPS), has the responsibility to retrieve, stage, pretreat, and deliver feed directly to the WTP Low Activity Waste (LAW) Vitrification Facility. The Direct Feed LAW (DFLAW) scenario is being considered by DOE as a strategy to treat Hanford tank wastes as soon as practicable. Extensive planning is underway by One System, an effort with joint participation by WTP and TOC personnel. The initial focus of One System is to achieve the required integration to ensure the waste feed meets acceptance requirements for processing in the TOC Low Activity Waste Pretreatment System (LAWPS) and WTP LAW facilities. The integrated waste feed qualification program approach for DFLAW was defined by One System during a four-day workshop. The effort resulted in a feasible approach for integrating LAWPS and LAW feed acceptance requirements to vitrify low-activity waste while complying with facility design basis, safety basis, waste acceptance criteria, and glass product compliance. The defined qualification program will provide a systematic approach to test newly staged feed campaigns at bench-scale using actual tank waste samples. The required integration and basis for obtaining sufficient and necessary data to qualify the feed for DFLAW facilities are discussed in this paper. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Low- and Intermediate-Active Waste Management in the Federal Republic of Germany - 16567

Waste with negligible heat generation (low- and intermediate-active waste) generated in Germany is to be emplaced in the Konrad repository. As the start of operation of the Konrad repository is expected in 2022, regulations have been developed that allow a longer storage period while keeping the same high level of safety. The guidelines for the storage of radioactive waste with negligible heat-generation have become part of the regulatory framework and its enforcement is thoroughly guided by the responsible Federal Ministry. Radioactive waste generated during the operation or the decommissioning of nuclear power plants and nuclear fuel cycle facilities has to be stored by the operator until the Konrad repository is available. In contrast, radioactive waste generated from other industrial, medical and research applications including spent nuclear sources, initially has to be delivered to a Land collecting facility and has to be registered, treated and stored there. The Land collecting facilities will deliver the resulting waste packages to the disposal facility as of 2022. While the operation of the Land Collecting Facilities is a task of the responsible Laender authorities, the operation of the repository Konrad is a federal task. The interaction of the involved different parties will be described. This paper will focus on the management of low- and intermediate-active waste. It will give an insight to the expected amounts and different kinds of waste streams. The different concepts for collecting and qualification procedures for waste packages depending on the origin of the waste will be presented. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

Public perception of hazardousness caused by current trends of municipal solid waste management

Highlights: • Contribution to the scientific literature by examining the relationship between concern for the environment and waste disposal in the frame of household waste treatment mechanism specifically in developing countries. • The awareness of the citizens satisfaction level and the local existing capacities in developing countries significantly contribute to decision making on MSW management sustainability in Palestine and other developing countries when applied. • Identification of the differences and similarities among DC resulting to failures or success in WM field. - Abstract: Municipal solid waste (MSW) piling up is becoming a serious problem in all developing countries (DC) as a result of inequitable waste collection and treatment. Citizens’ collaboration is partly based on understanding their views and their active involvement in MSW planning; on the other hand the assessment of the perception of hazardousness related with MSW is considered rather important as well since the identification of the weak points of the applied MWM strategy is eased and the level of required training is determined. Researchers implemented a case study in the West Bank (WB) and Gaza Strip (GS) regions of Palestine, taking into consideration previous researches in other developing countries. They reached to safe and useful conclusions regarding the parameters which mean the greatest in the waste management field as far as DC are concerned. Lack of skilled manpower, irregular collection services, inadequate equipment used for waste collection, inadequate legal provisions, and resource constraints are additional factors that are confirmed to be challenging the waste management scenarios in all DCs today. The research takes those factors under consideration but focuses on the educational gap and the results revealed interesting trends a significant relationship between respondent’s educational attainment and their awareness of hazardous waste (hazard perception); the results will indicate the measure taking required to avoid accidents occurred in those regions (burns from toxics, cuts from sharps, etc). National policy and legislation development based on the research outcomes will ensure equitable and accessible services are in place in order to move towards a healthier environment. Specialized health education and training programs on national scale are also needed to enhance awareness on hazardous waste.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

The On-line Waste Library (OWL): Usage and Inventory Status Report

The Waste Form Disposal Options Evaluation Report (SNL 2014) evaluated disposal of both Commercial Spent Nuclear Fuel (CSNF) and DOE-managed HLW and Spent Nuclear Fuel (DHLW and DSNF) in the variety of disposal concepts being evaluated within the Used Fuel Disposition Campaign. That work covered a comprehensive inventory and a wide range of disposal concepts. The primary goal of this work is to evaluate the information needs for analyzing disposal solely of a subset of those wastes in a Defense Repository (DRep; i.e., those wastes that are either defense related, or managed by DOE but are not commercial in origin). A potential DRep also appears to be safe in the range of geologic mined repository concepts, but may have different concepts and features because of the very different inventory of waste that would be included. The focus of this status report is to cover the progress made in FY16 toward: (1) developing a preliminary DRep included inventory for engineering/design analyses; (2) assessing the major differences of this included inventory relative to that in other analyzed repository systems and the potential impacts to disposal concepts; (3) designing and developing an on-line waste library (OWL) to manage the information of all those wastes and their waste forms (including CSNF if needed); and (4) constraining post-closure waste form degradation performance for safety assessments of a DRep. In addition, some continuing work is reported on identifying potential candidate waste types/forms to be added to the full list from SNL (2014 – see Table C-1) which also may be added to the OWL in the future. The status for each of these aspects is reported herein.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

Westinghouse Cementation Facility of Solid Waste Treatment System - 13503

During NPP operation, several waste streams are generated, caused by different technical and physical processes. Besides others, liquid waste represents one of the major types of waste. Depending on national regulation for storage and disposal of radioactive waste, solidification can be one specific requirement. To accommodate the global request for waste treatment systems Westinghouse developed several specific treatment processes for the different types of waste. In the period of 2006 to 2008 Westinghouse awarded several contracts for the design and delivery of waste treatment systems related to the latest CPR-1000 nuclear power plants. One of these contracts contains the delivery of four Cementation Facilities for waste treatment, s.c. 'Follow on Cementations' dedicated to three locations, HongYanHe, NingDe and YangJiang, of new CPR-1000 nuclear power stations in the People's Republic of China. Previously, Westinghouse delivered a similar cementation facility to the CPR-1000 plant LingAo II, in Daya Bay, PR China. This plant already passed the hot functioning tests successfully in June 2012 and is now ready and released for regular operation. The 'Follow on plants' are designed to package three 'typical' kind of radioactive waste: evaporator concentrates, spent resins and filter cartridges. The purpose of this paper is to provide an overview on the Westinghouse experience to design and execution of cementation facilities. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Radioactive Waste Management in HANARO (High Flux Advanced Neutron Application Reactor) - 16076

HANARO (High Flux Advanced Neutron Application Reactor) is a research reactor at the Korea Atomic Energy Research Institute (KAERI). Currently, it is the only research reactor generating a high neutron flux for neutron science and technology and the production of radioisotopes in Korea. Various kinds of radioactive wastes such as wastewater, spent ion exchange resins, solid waste and gaseous waste are generated from HANARO, as in other nuclear reactors. The most important feature of the radioactive waste in HANARO is that some radioactive waste is contaminated with tritium because HANARO uses heavy water as a reflector. At present, the waste generated from HANARO is transferred to and treated or stored at the Radioactive Waste Treatment Facility (RWTF) of KAERI. However, the RWTF does not have proper technology to treat radioactive waste contaminated with tritium from HANARO. Therefore, it is imperative to have a proper means to reduce the amount of radioactive waste and handle it more safely. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

In-Can Melter for Vitrification of Waste Coming from Decommissioning and Dismantling Operations - 19020

Some waste streams from decommissioning and dismantling operations are identified as an issue in terms of handling, transportation, adapted conditioning matrix or evacuation outlet within the existing regulations. In this context, the consortium of the DEM and MELT project which gathers Orano, the CEA and ECM technologies are currently developing and qualifying a specific vitrification tool designed to match the requirements and constraints of D and D projects. The main characteristics of this In-Can vitrification process are presented hereafter: - Suitable for high or medium level waste; - Flexible enough to accommodate uncertainties on waste composition; - Adequately dimensioned and compact to be implemented and operated inside an existing cell or close to the waste to be treated; - Designed for a short duration of use, as a decommissioning tool, aimed to be dismantled just after the treatment operation; - Designed in order to produce a small amount of secondary waste; - Requiring low investment and operation costs. The In-Can melting process has already been developed by the CEA for an internal application (defense waste vitrification) and can be rated TRL 7. That means it has been tested at full scale at a prototypical demonstration level with a range of simulants in an operational environment. This paper presents the In-Can vitrification process and its performances for a typical D and D waste highly loaded with Cs. The vitrification tests results will be in particular discussed in terms of process parameters, glass properties and cesium volatility. This paper also highlights the methodology and the organization (material, process, technological and long term behavior teams) deployed in order to adapt and qualify the In-Can process for all kind of wastes (liquid, solid, highly loaded with Tc and Cs, waste with no route, ...) from the matrix design definition to the full qualification. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗