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Sample records for alternate storage facility

  1. SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    RUTHERFORD WW; GEUTHER WJ; STRANKMAN MR; CONRAD EA; RHOADARMER DD; BLACK DM; POTTMEYER JA

    2009-04-29

    The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is

  2. SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS. ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY

    International Nuclear Information System (INIS)

    The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is

  3. Spent unreprocessed fuel (SURF) facility evaluation plan of the alternative storage concepts

    International Nuclear Information System (INIS)

    Concepts were evaluated for the storage of unreprocessed spent fuel in a retrievable surface storage facility. This document provides a systematic format for making a concept selection from the seven alternative concepts presented in RHO-LD-2. Results of the evaluation was that the Drywell concept was rated highest with the Water Basin Concept and the Sealed Storage Cask concept with multiple canisters of SURF coming in a close second and third

  4. Conceptual design report: Nuclear materials storage facility renovation. Part 6, Alternatives study

    International Nuclear Information System (INIS)

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for material and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment 111-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VI - Alternatives Study, presents a study of the different storage/containment options considered for NMSF

  5. Oil Storage Facilities - Storage Tank Locations

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — A Storage Tank Location is a DEP primary facility type, and its sole sub-facility is the storage tank itself. Storage tanks are aboveground or underground, and are...

  6. Spent-fuel-storage alternatives

    International Nuclear Information System (INIS)

    The Spent Fuel Storage Alternatives meeting was a technical forum in which 37 experts from 12 states discussed storage alternatives that are available or are under development. The subject matter was divided into the following five areas: techniques for increasing fuel storage density; dry storage of spent fuel; fuel characterization and conditioning; fuel storage operating experience; and storage and transport economics. Nineteen of the 21 papers which were presented at this meeting are included in this Proceedings. These have been abstracted and indexed

  7. Spent-fuel-storage alternatives

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    The Spent Fuel Storage Alternatives meeting was a technical forum in which 37 experts from 12 states discussed storage alternatives that are available or are under development. The subject matter was divided into the following five areas: techniques for increasing fuel storage density; dry storage of spent fuel; fuel characterization and conditioning; fuel storage operating experience; and storage and transport economics. Nineteen of the 21 papers which were presented at this meeting are included in this Proceedings. These have been abstracted and indexed. (ATT)

  8. Multipurpose dry storage facilities

    International Nuclear Information System (INIS)

    SGN has gained considerable experience in the design and construction of interim storage facilities for spent fuel and various nuclear waste, and can therefore propose single product and multiproduct facilities capable of accommodating all types of waste in a single structure. The pooling of certain functions (transport cask reception, radiation protection), the choice of optimized technologies to meet the specific needs of the clients (automatic transfer by shielded cask or nuclearized crane) and the use of the same type of well to cool the heat releasing packages (glass canisters, fuel elements) make it possible to propose industrially proven and cost effective solutions. The studies conducted by SGN on behalf of the Dutch company COVRA (Centrale Organisatie Voor Radioactif Afval), offer an example of the application of this new concept. This paper first presents the SGN experience through a short description of reference storage facilities for various types of products (MLW, HLW and Spent Fuel). It goes on with a typical application to show how these proven technologies are combined to obtain single product or multiproduct facilities tailored to the client's specific requirements. (author)

  9. High-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy eenvironmental management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    This report provides data and information needed to support the risk and impact assessments of high-level waste (HLW) management alternatives in the U.S. Department of Energy Waste Management (WM) Programmatic Environmental Impact Statement (PEIS). Available data on the physical form, chemical and isotopic composition, storage locations, and other waste characteristics of interest are presented. High-level waste management follows six implementation phases: current storage, retrieval, pretreatment, treatment, interim canister storage, and geologic repository disposal; pretreatment, treatment, and repository disposal are outside the scope of the WM PEIS. Brief descriptions of current and planned HLW management facilities are provided, including information on the type of waste managed in the facility, costs, product form, resource requirements, emissions, and current and future status. Data sources and technical and regulatory assumptions are identified. The range of HLW management alternatives (including decentralized, regionalized, and centralized approaches) is described. The required waste management facilities include expanded interim storage facilities under the various alternatives. Resource requirements for construction (e.g., land and materials) and operation (e.g., energy and process chemicals), work force, costs, effluents, design capacities, and emissions are presented for each alternative

  10. High-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Environmental Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    This report provides data and information needed to support the risk and impact assessments of high-level waste (HLW) management alternatives in the US Department of Energy Waste Management (WM) Programmatic Environmental Impact Statement (PEIS). Available data on the physical form, chemical and isotopic composition, storage locations, and other waste characteristics of interest are presented. High-level waste management follows six implementation phases: current storage, retrieval, pretreatment, treatment, interim canister storage, and geologic repository disposal; pretreatment, treatment, and repository disposal are outside the scope of the WM PEIS. Brief descriptions of current and planned HLW management facilities are provided, including information on the type of waste managed in the facility, costs, product form, resource requirements, emissions, and current and future status. Data sources and technical and regulatory assumptions are identified. The range of HLW management alternatives (including decentralized, regionalized, and centralized approaches) is described. The required waste management facilities include expanded interim storage facilities under the various alternatives. Resource requirements for construction (e.g., land and materials) and operation (e.g., energy and process chemicals), work force, costs, effluents, design capacities, and emissions are presented for each alternative

  11. Spent fuel storage facility

    International Nuclear Information System (INIS)

    A diffusion-preventive device for the radioactivity of pool water is disposed in a pool chamber for accommodating a spent fuel storage chamber. The diffusion-preventive device comprises an air washer and a recycling blower which discharges air in the air washer to the pool chamber. In this air washer, not-activated pure water, etc. are supplied. The recycling blower is driven to introduce the air in the pool chamber to the air washer, and water is sprayed from a nozzle to moisten the air. In this way, the vapor pressure in the pool chamber can be increased and the amount of vapor generated from the pool can be decreased. The amount of radioactivity transferring from the poor water to the air can thereby be decreased and the amount of radioactivity released to the atmospheric air by means of ventilation air conditioning device can be decreased. (I.N.)

  12. Monitored retrievable storage facility (MRS)

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) contracts with Management and Operations (M ampersand O) contractors to provide design and support for Monitored Retrievable Storage Facilities (MRS). This paper outlines the steps taken by the M ampersand O contractor in the design and siting process for MRS facilities. These steps include conceptual, preliminary and final MRS design, evaluation and selection of storage technologies, developing a safety analysis report (SAR) and completing the facility license application. After the preliminary work is done, a M ampersand O support group assures licensing, siting, and community outreach. The community outreach or public relations includes information about the MRS in layman's terms so that DOE will get feed back from the community

  13. An alternative storage method for entomopathogenic nematodes

    OpenAIRE

    GÜLCÜ, Barış; HAZIR, Selçuk

    2012-01-01

    Tetra Pak containers were evaluated as an alternative to tissue culture flasks for nematode storage. Our data showed that Tetra Pak containers were an excellent alternative to tissue culture flasks for storage of H. bacteriophora and will more than likely be useful for other entomopathogenic nematode species.

  14. Hazardous waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    This report focuses on the generation of hazardous waste (HW) and the treatment, storage, and disposal (TSD) of HW being generated by routine US Department of Energy (DOE) facility operations. The wastes to be considered are managed by the DOE Waste Management (WM) Division (WM HW). The waste streams are to be sent to WM operations throughout the DOE complex under four management alternatives: No Action, Decentralization, Regionalized 1, and Regionalized 2. On-site and off-site capabilities for TSD are examined for each alternative. This report (1) summarizes the HW inventories and generated amounts resulting from WM activities, focusing on the largest DOE HW generators; (2) presents estimates of the annual amounts shipped off-site, as well as the amounts treated by various treatment technology groups; (3) describes the existing and planned treatment and storage capabilities of the largest HW-generating DOE installations, as well as the use of commercial TSD facilities by DOE sites; (4) presents applicable technologies (destruction of organics, deactivation/neutralization of waste, removal/recovery of organics, and aqueous liquid treatment); and (5) describes the four alternatives for consideration for future HW management, and for each alternative provides the HW loads and the approach used to estimate the source term for routine TSD operations. In addition, potential air emissions, liquid effluents, and solid residuals associated with each alternative are presented. Furthermore, this report is supplemented with an addendum that includes detailed information related to HW inventory, characteristics, generation, and facility assessment for the TSD alternatives. The addendum also presents source terms, emission rates, and throughput totals by alternative and treatment installation

  15. Dry storage of spent fuel elements: interim facility

    International Nuclear Information System (INIS)

    Apart from the existing facilities to storage nuclear fuel elements at Argentina's nuclear power stations, a new interim storage facility has been planned and projected by the Argentinean Atomic Energy Commission (CNEA) that will be constructed by private group. This article presents the developments and describes the activities undertaken until the national policy approach to the final decision for the most suitable alternative to be adopted. (B.C.A.). 09 refs, 01 fig, 09 tabs

  16. Bidding strategy for an energy storage facility

    DEFF Research Database (Denmark)

    Nasrolahpour, Ehsan; Zareipour, Hamidreza; Rosehart, William D.;

    2016-01-01

    This paper studies operation decisions of energy storage facilities in perfectly and imperfectly competitive markets. In a perfectly competitive market, the storage facility is operated to maximize the social welfare. However, in a imperfectly competitive market, the storage facility operates to...... maximize its profit, while the market operator aims at maximizing the social welfare. In this case, the storage facility adapts its strategic behavior to take advantage of market conditions. To model the imperfectly competitive market, a bi-level optimization model is implemented to present the...... interactions between the storage facility and the market operator. In an illustrative test system, operation of the storage facility in these two market structures is compared and discussed....

  17. Heat generating waste storage facility

    International Nuclear Information System (INIS)

    A heat generating waste storage facility comprises an air flow regulating plug and a plug position control mechanism. When heat generation wastes are contained only in small number of containing tubes, the air flow regulator plugs of the containing tubes incorporated with heat generating wastes are raised, and air discharge holes are exposed from the upper end of the containing tube. The flow regulating plugs of the containing tubes not incorporated with heat generating waste are lowered, and the upper ends of the containing tubes are closed by closing members. Then, air streams are circulated only to the containing tubes incorporated with heat generation wastes. This can minimize the amount of the air flow of the air supply blowers and air exhaustion blowers thereby enabling to reduce the running cost. (N.H.)

  18. Alternatives for water basin spent fuel storage using pin storage

    International Nuclear Information System (INIS)

    The densest tolerable form for storing spent nuclear fuel is storage of only the fuel rods. This eliminates the space between the fuel rods and frees the hardware to be treated as non-fuel waste. The storage density can be as much as 1.07 MTU/ft2 when racks are used that just satisfy the criticality and thermal limitations. One of the major advantages of pin storage is that it is compatible with existing racks; however, this reduces the storage density to 0.69 MTU/ft2. Even this is a substantial increase over the 0.39 MTU/ft2 that is achievable with current high capacity stainless steel racks which have been selected as the bases for comparison. Disassembly requires extensive operation on the fuel assembly to remove the upper end fitting and to extract the fuel rods from the assembly skeleton. These operations will be performed with the aid of an elevator to raise the assembly where each fuel rod is grappled. Lowering the elevator will free the fuel rod for transfer to the storage canister. A storage savings of $1510 per MTU can be realized if the pin storage concept is incorporated at a new away-from-reactor facility. The storage cost ranges from $3340 to $7820 per MTU of fuel stored with the lower cost applying to storage at an existing away-from-reactor storage facility and the higher cost applying to at-reactor storage

  19. Alternative design concept for the second Glass Waste Storage Building

    Energy Technology Data Exchange (ETDEWEB)

    Rainisch, R.

    1992-10-01

    This document presents an alternative design concept for storing canisters filled with vitrified waste produced at the Defense Waste Processing Facility (DWPF). The existing Glass Waste Storage Building (GWSB1) has the capacity to store 2,262 canisters and is projected to be completely filled by the year 2000. Current plans for glass waste storage are based on constructing a second Glass Waste Storage Building (GWSB2) once the existing Glass Waste Storage Building (GWSB1) is filled to capacity. The GWSB2 project (Project S-2045) is to provide additional storage capacity for 2,262 canisters. This project was initiated with the issue of a basic data report on March 6, 1989. In response to the basic data report Bechtel National, Inc. (BNI) prepared a draft conceptual design report (CDR) for the GWSB2 project in April 1991. In May 1991 WSRC Systems Engineering issued a revised Functional Design Criteria (FDC), the Rev. I document has not yet been approved by DOE. This document proposes an alternative design for the conceptual design (CDR) completed in April 1991. In June 1992 Project Management Department authorized Systems Engineering to further develop the proposed alternative design. The proposed facility will have a storage capacity for 2,268 canisters and will meet DWPF interim storage requirements for a five-year period. This document contains: a description of the proposed facility; a cost estimate of the proposed design; a cost comparison between the proposed facility and the design outlined in the FDC/CDR; and an overall assessment of the alternative design as compared with the reference FDC/CDR design.

  20. Hazardous waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    This report focuses on the generation of hazardous waste (HW) and the treatment of HW being generated by routine US Department of Energy (DOE) facility operations. The wastes to be considered are managed by the DOE Waste Management (WM) Division (WM HW). The waste streams are to be sent to WM operations throughout the DOE complex under four management alternatives: No Action, Decentralization, Regionalized 1, and Regionalized 2. On-site and off-site capabilities for treatment are examined for each alternative. This report (1) summarizes the HW inventories and generated amounts resulting from WM activities, focusing on the largest DOE HW generators; (2) presents estimates of the annual amounts shipped off-site, as well as the amounts treated by various treatment technology groups; (3) describes the existing and planned treatment and storage capabilities of the largest HW-generating DOE installations, as well as the use of commercial treatment facilities by DOE sites; (4) presents applicable technologies (destruction of organics, deactivation/neutralization of waste, removal/recovery of organics, and aqueous liquid treatment); and (5) describes the four alternatives for consideration for future HW management, and for each alternative provides the HW loads and the approach used to estimate the source term for routine treatment operations. In addition, potential air emissions, liquid effluents, and solid residuals associated with each alternative are presented. This report is supplemented with an addendum that includes detailed information related to HW inventory, characteristics, generation, and facility assessment for the treatment alternatives. The addendum also presents source terms, emission rates, and throughput totals by alternative and treatment installation

  1. Interim Storage Facility decommissioning. Final report

    International Nuclear Information System (INIS)

    Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

  2. Technological alternatives for plutonium storage

    International Nuclear Information System (INIS)

    This paper discusses the problems of large long term storage since stores at fabrication plants may depend on the form of plutonium ultimately chosen for transport. The paper's conclusion includes: MOX can be regarded as more proliferation resistant than PUO2 but no experience of long term storage is available, therefore further R and D is required; co-location of the store with reprocessing plants (and fuel fabrication plant) would appear to have advantages in non-proliferation, safeguards implementation, environmental protection and economic aspects; there are strong non-proliferation and security arguments for not moving plutonium away from the site where it was separated until there is an identifiable and scheduled end use. The design of the store, the form in which plutonium should be stored, particularly as MOX, and the costs and further R and D required are considered. The possible location of stores is also discussed and institutional questions briefly considered

  3. Mixed oxide conversion facility alternative conceptual designs

    International Nuclear Information System (INIS)

    Allied-General Nuclear Services recently performed studies to evaluate alternative proliferation-resistant flowsheets of the uranium-based LWR fuel cycle. The alternatives evaluated consist of coprocessing schemes with either a gamma or a heat spike added. A literature search and evaluation were performed to select a process technology for mixed oxide coconversion. The COPRECAL process was chosen as the most suitable conversion process technology. Three alternative mixed oxide conversion facility design concepts were prepared based on the COPRECAL technology. These alternative concepts are compared to a pure plutonium conversion facility. Facility designs, relative proliferation resistance, and cost estimates are discussed

  4. Dry Well Storage Facility conceptual design study

    International Nuclear Information System (INIS)

    The Dry Well Storage Facility described is assumed to be located adjacent to or near a Spent Fuel Receiving and Packaging Facility and/or a Packaged Fuel Transfer Facility. Performance requirements, quality levels and codes and standards, schedule and methods of performance, special requirements, quality assurance program, and cost estimate are discussed. Appendices on major mechanical equipment and electric power requirements are included

  5. Design of spent fuel storage facilities

    International Nuclear Information System (INIS)

    This Safety Guide is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes the general safety requirements applicable to the design of both wet and dry spent fuel storage facilities; Section 3 deals with the design requirements specific to either wet or dry storage. Recommendations for the auxiliary systems of any storage facility are contained in Section 4; these are necessary to ensure the safety of the system and its safe operation. Section 5 provides recommendations for establishing the quality assurance system for a storage facility. Section 6 discusses the requirements for inspection and maintenance that must be considered during the design. Finally, Section 7 provides guidance on design features to be considered to facilitate eventual decommissioning. 18 refs

  6. Preliminary assessment of alternative dry storage methods for the storage of commercial spent nuclear fuel

    International Nuclear Information System (INIS)

    This report presents the results of an assessment of the (1) state of technology, (2) licensability, (3) implementation schedule, and (4) costs of alternative dry methods for storage of spent fuel at a reactor location when used to supplement reactor pool storage facilities. The methods of storage that were considered included storage in casks, drywells, concrete silos and air-cooled vaults. The impact of disassembly of spent fuel and storage of consolidated fuel rods was also determined. The economic assessments were made based on the current projected storage requirements of Virginia Electric and Power Company's Surry Station for the period 1985 to 2009, which has two operating pressurized water reactors (824 MWe each). It was estimated that the unit cost for storage of spent fuel in casks would amount to $117/kgU and that such costs for storage in drywells would amount to $137/kgU. However, based on the overall assessment it was concluded both storage methods were equal in merit. Modular methods of storage were generally found to be more economic than those requiring all or most of the facilities to be constructed prior to commencement of storage operations

  7. Onsite storage facility for low level radwaste

    International Nuclear Information System (INIS)

    The Tennessee Valley Authority (TVA) has designed and constructed an onsite storage facility for low level radwaste (LLRW) at its Browns Ferry Nuclear Plant in northern Alabama. The paper addresses the function of this facility and provides a complete description of the reinforced concrete storage modules which are the principal structural elements of the facility. The loads and loading combinations for the design of the storage modules are defined to include the foundation design parameters. Other aspects of the modules that are addressed are; the structural roof elements that provide access to the modules, shielding requirements for the LLRW, and tornado missile considerations

  8. Storage facility for radioactive material

    International Nuclear Information System (INIS)

    In an underground type storage chamber for horizontally storing storage vessels made of steel having radioactive materials sealed therein and cooling them by spontaneous ventilation, the storage vessels made of steel are stored in multi-layers in vertical direction. In addition, lifts for transferring casks which transfer the storage vessels made of steel from a nuclear power plant are made movable in vertical and horizontal directions in the underground type storage chamber. In addition, the storage chamber is partitioned so that the air for cooling radioactive materials flows in parallel with or perpendicular to the storage vessels made of steel. Since the storage vessels can be stored in multi-layers, the density upon storing the spent fuels and high level radioactive wastes can be increased. In addition, protection against external flying objects such as crush of air crafts can be attained neither increasing the thickness of the walls of a building excessively nor specifying the shape of the construction site. (N.H.)

  9. Storage facility for radioactive wastes

    International Nuclear Information System (INIS)

    Canisters containing high level radioactive wastes are sealed in overpacks in a receiving building constructed on the ground. A plurality of storage pits are formed in a layered manner vertically in multi-stages in deep underground just beneath the receiving building, for example underground of about 1000m from the ground surface. Each of the storage pits is in communication with a shaft which vertically communicates the receiving building and the storage pits, and is extended plainly in a horizontal direction from the shaft. The storage pit comprises an overpack receiving chamber, a main gallery and a plurality of galleries. A plurality of holes for burying the overpacks are formed on the bottom of the galleries in the longitudinal direction of the galleries. A plurality of overpack-positioning devices which run in the main gallery and the galleries by remote operation are disposed in the main gallery and the galleries. (I.N.)

  10. Regional spent fuel storage facility (RSFSF)

    International Nuclear Information System (INIS)

    The paper gives an overview of the meetings held on the technology and safety aspects of regional spent fuel storage facilities. The questions of technique, economy and key public and political issues will be covered as well as the aspects to be considered for implementation of a regional facility. (author)

  11. Interim storage facility for spent fuel

    International Nuclear Information System (INIS)

    The spent fuel generated from the operation of a nuclear power plant is to be treated in the reprocessing plant in Rokkasho, Aomori. At present, spent fuel is stored in the nuclear power plant until it is reprocessed. However the amount of spent fuel generated exceeds the capacity of the reprocessing plant. Hence an additional spent fuel storage facility is needed for the nuclear fuel cycle. The spent fuel interim storage facility is the first institution in Japan that stores spent fuel outside of the nuclear power plant site. Our company has received an order for internal equipment for this facility. This paper introduces an overview of the interim storage facility for spent fuel. (author)

  12. Operation of spent fuel storage facilities

    International Nuclear Information System (INIS)

    This Safety Guide was prepared as part of the IAEA's programme on safety of spent fuel storage. This is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes key activities in the operation of spent fuel storage facilities. Section 3 lists the basic safety considerations for storage facility operation, the fundamental safety objectives being subcriticality, heat removal and radiation protection. Recommendations for organizing the management of a facility are contained in Section 4. Section 5 deals with aspects of training and qualification; Section 6 describes the phases of the commissioning of a spent fuel storage facility. Section 7 describes operational limits and conditions, while Section 8 deals with operating procedures and instructions. Section 9 deals with maintenance, testing, examination and inspection. Section 10 presents recommendations for radiation and environmental protection. Recommendations for the quality assurance (QA) system are presented in Section 11. Section 12 describes the aspects of safeguards and physical protection to be taken into account during operations; Section 13 gives guidance for decommissioning. 15 refs, 5 tabs

  13. 303-K Storage Facility closure plan

    International Nuclear Information System (INIS)

    Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5

  14. Calcined solids storage facility closure study

    Energy Technology Data Exchange (ETDEWEB)

    Dahlmeir, M.M.; Tuott, L.C.; Spaulding, B.C. [and others

    1998-02-01

    The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a {open_quotes}Settlement Agreement{close_quotes} (or {open_quotes}Batt Agreement{close_quotes}) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed.

  15. Calcined solids storage facility closure study

    International Nuclear Information System (INIS)

    The disposal of radioactive wastes now stored at the Idaho National Engineering and Environmental Laboratory is currently mandated under a open-quotes Settlement Agreementclose quotes (or open-quotes Batt Agreementclose quotes) between the Department of Energy and the State of Idaho. Under this agreement, all high-level waste must be treated as necessary to meet the disposal criteria and disposed of or made road ready to ship from the INEEL by 2035. In order to comply with this agreement, all calcined waste produced in the New Waste Calcining Facility and stored in the Calcined Solids Facility must be treated and disposed of by 2035. Several treatment options for the calcined waste have been studied in support of the High-Level Waste Environmental Impact Statement. Two treatment methods studied, referred to as the TRU Waste Separations Options, involve the separation of the high-level waste (calcine) into TRU waste and low-level waste (Class A or Class C). Following treatment, the TRU waste would be sent to the Waste Isolation Pilot Plant (WIPP) for final storage. It has been proposed that the low-level waste be disposed of in the Tank Farm Facility and/or the Calcined Solids Storage Facility following Resource Conservation and Recovery Act closure. In order to use the seven Bin Sets making up the Calcined Solids Storage Facility as a low-level waste landfill, the facility must first be closed to Resource Conservation and Recovery Act (RCRA) standards. This study identifies and discusses two basic methods available to close the Calcined Solids Storage Facility under the RCRA - Risk-Based Clean Closure and Closure to Landfill Standards. In addition to the closure methods, the regulatory requirements and issues associated with turning the Calcined Solids Storage Facility into an NRC low-level waste landfill or filling the bin voids with clean grout are discussed

  16. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bonnema, Bruce Edward

    2001-09-01

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  17. Gas storage facilities. Investigation of their social value

    International Nuclear Information System (INIS)

    The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm3 gas to 650 Mm3. Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

  18. Gas storage facilities. Investigation of their social value. Supplement

    International Nuclear Information System (INIS)

    The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm3 gas to 650 Mm3. Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

  19. Calcine Conversion Facility alternative concepts engineering studies

    International Nuclear Information System (INIS)

    The purpose of the engineering study reported is to develop conceptual designs for two alternative facilities for the conversion of high level waste calcine to high level glass. The objectives and design bases of the two concepts (CCF/RSSF and CCF/FRP) are described. No recommendation of one concept in preference to the other is given. (LK)

  20. The cascad spent fuel dry storage facility

    International Nuclear Information System (INIS)

    France has a wide variety of experimental spent fuels different from LWR spent fuel discharged from commercial reactors. Reprocessing such fuels would thus require the development and construction of special facilities. The French Atomic Energy Commission (CEA) has consequently opted for long-term interim storage of these spent fuels over a period of 50 years. Comparative studies of different storage concepts have been conducted on the basis of safety (mainly containment barriers and cooling), economic, modular design and operating flexibility criteria. These studies have shown that dry storage in a concrete vault cooled by natural convection is the best solution. A research and development program including theoretical investigations and mock-up tests confirmed the feasibility of cooling by natural convection and the validity of design rules applied for fuel storage. A facility called CASCAD was built at the CEA's Cadarache Nuclear Research Center, where it has been operational since mid-1990. This paper describes the CASCAD facility and indicates how its concept can be applied to storage of LWR fuel assemblies

  1. Concepts for Waste Retrieval and Alternate Storage of Radioactive Waste

    International Nuclear Information System (INIS)

    The primary purpose of this technical report is to present concepts for retrieval operations, equipment to be used, scenarios under which waste retrieval operations will take place, methods for responding to potential retrieval problems, and compliance with the preclosure performance objectives of 10 CFR 63.111(a) and (b) [DIRS 156605] during the retrieval of waste packages from the subsurface repository. If a decision for retrieval is made for any or all of the waste, the waste to be retrieved would be dispositioned in accordance with the regulations applicable at the time. The secondary purpose is to present concepts for the design, construction, and operation of an alternate storage facility. The alternate storage facility would temporarily house the retrieved waste until final disposition is established. The concept presented is consistent with current practices and regulations for the protection of public health and safety and the environment, it demonstrates the feasibility of such a facility, if required, and it is based on the consideration for keeping radiation exposure as low as is reasonably achievable (ALARA)

  2. Monitored retrievable storage facility site screening and evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force.

  3. Monitored retrievable storage facility site screening and evaluation report

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force

  4. Preconceptual design for a Monitored Retrievable Storage (MRS) transfer facility

    International Nuclear Information System (INIS)

    The contract between the DOE and the utilities specifies that the DOE will receive spent fuel from the nuclear utilities in 1998. This study investigates the feasibility of employing a simple Transfer Facility which can be constructed quickly, and operate while the full-scale MRS facilities are being constructed. The Transfer Facility is a hot cell designed only for the purpose of transferring spent fuel assemblies from the Office of Civilian Radioactive Waste Management (OCRWM) transport casks (shipped from the utility sites) into onsite concrete storage casks. No operational functions other than spent fuel assembly transfers and the associated cask handling, opening, and closing would be performed in this facility. Radioactive waste collected in the Transfer Facility during operations would be stored until the treatment facilities in the full-scale MRS facility became operational, approximately 2 years after the Transfer Facility started operation. An alternate wherein the Transfer Facility was the only waste handling building on the MRS site was also examined and evaluated. 6 figs., 26 tabs

  5. Continuous inventory in SNM storage facilities

    International Nuclear Information System (INIS)

    Instrumentation and data processing techniques that provide inexpensive verification of material in storage were investigated. Transfers of special nuclear materials (SNM) into the storage area are accompanied by an automated verification of the container identity, weight, and the radiation signature of the contents. This information is computer-processed and stored for comparison at subsequent transfers and also provides the data base for record purposes. Physical movement of containers across the boundary of the storage area is presently accomplished by operating personnel in order to minimize expensive modifications to existing storage facilities. Personnel entering and leaving the storage area are uniquely identified and also through portal monitors capable of detecting small quantities of SNM. Once material is placed on the storage shelves, simple, low-cost container tagging and radiation sensors are activated. A portion of the prescribed gamma signature, obtained by duplicate shelf monitors during the transfer verification, is thus continuously checked against the stored identification data. Radiation detector design is severely constrained by the need to discriminate individual signatures in a high background area and the need for low unit costs. In operation any unauthorized change in signal is analyzed along with auxiliary data from surveillance sensors to activate the appropriate alarms. (auth))

  6. Safety assessment for spent fuel storage facilities

    International Nuclear Information System (INIS)

    This Safety Practice has been prepared as part of the IAEA's programme on the safety assessment of interim spent fuel storage facilities which are not an integral part of an operating nuclear power plant. This report provides general guidance on the safety assessment process, discussing both deterministic and probabilistic assessment methods. It describes the safety assessment process for normal operation and anticipated operational occurrences and also related to accident conditions. 10 refs, 2 tabs

  7. CNAEM waste processing and storage facility

    International Nuclear Information System (INIS)

    Radioactive waste in Turkey is generated from various applications. Radioactive waste management activities are carried out in a facility at Cekmece Nuclear Research and Training Center (CNAEM). This facility has been assigned to take all low-level radioactive wastes generated by nuclear applications in Turkey. The wastes are generated from research and nuclear applications mainly in medicine, biology, agriculture, quality control in metal processing and construction industries. These wastes are classified as low- level radioactive wastes and their activities are up to 10-3 Ci/m3 (except spent sealed sources). Chemical treatment and cementation of liquid radwaste, segregation and compaction of solid wastes and conditioning of spent sources are the main processing activities of this facility. A.so, analyses, registration, quality control and interim storage of conditioned low-level wastes are the other related activities of this facility. Conditioned wastes are stored in an interim storage building. All waste management activities, which have been carried out in CNAEM, are generally described in this paper. (author)

  8. Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    International Nuclear Information System (INIS)

    DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft2 waste storage facility for RCRA waste, one 42,000 ft2 waste storage facility for toxic waste (TSCA), and one 200,000 ft2 mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required

  9. Monitored Retrievable Storage facility site screening and evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs {hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume.

  10. Monitored Retrievable Storage facility site screening and evaluation report

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume

  11. Monitored retrievable storage facility site screening and evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs{hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document.

  12. Monitored retrievable storage facility site screening and evaluation report

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document

  13. 36 CFR 1234.10 - What are the facility requirements for all records storage facilities?

    Science.gov (United States)

    2010-07-01

    ... requirements for all records storage facilities? 1234.10 Section 1234.10 Parks, Forests, and Public Property... FACILITIES Facility Standards § 1234.10 What are the facility requirements for all records storage facilities... specified in NFPA 13 (incorporated by reference, see § 1234.3). (2) An agency may request a waiver of...

  14. Alternatives for the disposition of fuel stored in the PUREX facility

    International Nuclear Information System (INIS)

    This document provides an evaluation of five alternatives for the disposition of 3.4 metric tons of irradiated fuel from PUREX to support facility turnover following deactivation. The alternatives for disposition of the fuel include transfer to the K Basins, transfer to T Plant, passivation and dry vault storage, and dissolution and underground tank storage. The five alternatives were compared and it was determined that the fuel should be transferred from PUREX to the K Basins where it would be placed into pool storage

  15. Immobilized High Level Waste (HLW) Interim Storage Alternative Generation and analysis and Decision Report 2nd Generation Implementing Architecture

    Energy Technology Data Exchange (ETDEWEB)

    CALMUS, R.B.

    2000-09-14

    Two alternative approaches were previously identified to provide second-generation interim storage of Immobilized High-Level Waste (IHLW). One approach was retrofit modification of the Fuel and Materials Examination Facility (FMEF) to accommodate IHLW. The results of the evaluation of the FMEF as the second-generation IHLW interim storage facility and subsequent decision process are provided in this document.

  16. 30 CFR 56.6130 - Explosive material storage facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Explosive material storage facilities. 56.6130... NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-SURFACE METAL AND NONMETAL MINES Explosives Storage § 56.6130 Explosive material storage facilities. (a) Detonators and explosives shall be stored...

  17. 30 CFR 57.6130 - Explosive material storage facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Explosive material storage facilities. 57.6130... NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Explosives Storage-Surface Only § 57.6130 Explosive material storage facilities. (a) Detonators and explosives...

  18. The Federal interim storage facility for radioactive waste under construction

    International Nuclear Information System (INIS)

    A short description of the design of the Federal interim storage facility for radioactive waste, the security aspects and the storage material is given. The interim storage facility is currently under construction in Wuerenlingen at the Paul Scherrer Institute. figs., tabs., 27 refs

  19. Occupational dose estimates for a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    Occupational doses were estimated for radiation workers at the monitored retrievable storage (MRS) facility. This study provides an estimate of the occupational dose based on the current MRS facility design, examines the extent that various design parameters and assumptions affect the dose estimates, and identifies the areas and activities where exposures can be reduced most effectively. Occupational doses were estimated for both the primary storage concept and the alternate storage concept. The dose estimates indicate the annual dose to all radiation workers will be below the 5 rem/yr federal dose equivalent limit. However, the estimated dose to most of the receiving and storage crew (the workers responsible for the receipt, storage, and surveillance of the spent fuel and its subsequent retrieval), to the crane maintenance technicians, and to the cold and remote maintenance technicians is above the design objective of 1 rem/yr. The highest annual dose is received by the riggers (4.7 rem) in the receiving and storage crew. An indication of the extent to which various design parameters and assumptions affect the dose estimates was obtained by changing various design-based assumptions such as work procedures, background dose rates in radiation zones, and the amount of fuel received and stored annually. The study indicated that a combination of remote operations, increased shielding, and additional personnel (for specific jobs) or changes in operating procedures will be necessary to reduce worker doses below 1.0 rem/yr. Operations that could be made at least partially remote include the removal and replacement of the tiedowns, impact limiters, and personnel barriers from the shipping casks and the removal or installation of the inner closure bolts. Reductions of the background dose rates in the receiving/shipping and the transfer/discharge areas may be accomplished with additional shielding

  20. High performance construction materials for treatment, storage, and disposal facilities

    International Nuclear Information System (INIS)

    Mixed hazardous/radioactive waste treatment, storage, and disposal (TSD) facilities are often required to either withstand harsh service environments or in the case of disposal facilities exhibit an extremely long service life. The default construction material, Portland cement based concrete (PCC) does not always meet the challenge. For example, many radioactive waste processing facilities are constructed with PCC and then lined with stainless steel. The stainless steel liner is added to provide a surface which can be decontaminated. Installation of the stainless steel liner is both expensive and labor intensive. Similarly, hazardous waste facilities generally require concrete surfaces to be lined with a material that reduces the permeability of the concrete and provides resistance to the harsh chemical environment prevalent in such facilities. This paper is a highly condensed report of the results of a research effort designed to expand the engineering knowledge on two alternate materials which exhibit properties that would allow them to replace the stainless steel lined concrete combination. The two materials are: (1) ICOM, a composite concrete made from a proprietary blend of resins, corrosion-resistant fillers and fine aggregates, and (2) sulfur concrete (SC) made from sulfur polymer cement (SPC). Both materials meet or exceed the mechanical and structural properties of PCC, with the added characteristic of impermeability. The experimental results which are briefly summarized below indicate that these materials are good candidates for applications where a PCC structure has traditionally required supplemental liners due to the poor performance of the PCC alone

  1. Status of siting the Monitored Retrievable Storage facility

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) is authorized to site, construct, and operate a Monitored Retrievable Storage (MRS) facility for temporary above ground storage of spent nuclear fuel from commercial reactors. The Nuclear Waste Policy Act (the Act) established two paths for obtaining a site. One, the DOE directed siting approach, is not being implemented at this time. Currently, DOE has decided to follow the second alternative, voluntary siting. The Act, as amended, also established the Office of the Nuclear Waste Negotiator (ONWN) to interact with potential volunteers who would host the MRS. The voluntary process has resulted in 21 applications for financial grants to study the possibility of hosting the facility. The siting process, regardless of the siting approach, must consider both statutory and regulatory requirements for the site. Preliminary site requirements and attributes can be used to assess the technical qualifications and regulatory compliance features of a potential MRS site. The site assessment process will determine whether a site meets the preliminary site requirements and attributes can be used to assess the technical qualifications and regulatory compliance features of a potential MRS site. The site assessment process will determine whether a site meets the preliminary site requirements and would identify the favorable and potentially unfavorable characteristics of a particular site. The purpose of these requirement and attributes is to permit a reasonable determination, on the basis of available information, that a site is potentially suitable for a MRS facility

  2. Transuranic waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE's Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal

  3. Transuranic waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy waste management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the U.S. Department of Energy (DOE) complex are important considerations in DOE's Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complexwide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into 10 TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the 10 TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal

  4. Managing Ageing in Spent Nuclear Fuel Storage Facilities

    International Nuclear Information System (INIS)

    Spent fuel pools (SFP) that are outside containment system without redundancy whose failure could release radioactive material that exceed allowable limit. If SFP have to continue to operate for long term after power plant shutdown it is essential to develop an ageing management program within the general life management program of the nuclear power plant. This work refers to the Atucha I nuclear power plant (NPP) SFPs. The fuel assembly (FA) of Atucha NPPs is 6 meter long and encompasses 36 Zircaloy-4 cladded fuel rods. For these spent fuel assemblies (SFA) there are two storage buildings located adjacent to the reactor building. One of the alternatives considered at the end of Atucha I operation is to transfer all SFAs to dry storage, another one is to continue the operation of the SFPs and to transfer to dry storage just a selected amount of SFAs. For the selection of the dry technology it should be kept in mind the characteristics of the Aturcha SFA, in particular, its length and burnup which differs according to the discharge date because of the use of natural uranium (NU) or slightly enriched uranium (SEU). Therefore, the fundamental point here is to keep in mind that it is the effect of ageing due to time and use that cause net changes in the characteristics of a System, Structure and Component (SSC). We employ formal processes to systematically identify and evaluate the Critical Systems, Structures and Components (CSSCs) in the facilities. A Technology Watch Programme is being established to ensure that degradation mechanisms, which could impact on facilities life, are promptly investigated so that mitigating programmes can be designed. With this methodology we analyse the following components of the pools, concrete wall stability, integrity of concrete structure, pool lining, and integrity of metal structure, pipe failures, degradation in storage racks and SFA degradation. (author)

  5. 46 CFR 108.237 - Fuel storage facilities.

    Science.gov (United States)

    2010-10-01

    ... Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) A-MOBILE OFFSHORE DRILLING UNITS DESIGN AND EQUIPMENT Construction and Arrangement Helicopter Facilities § 108.237 Fuel storage facilities. (a) Helicopter fuel storage tanks must be installed as far as practicable from— (1) The landing area; and...

  6. 18 CFR 157.213 - Underground storage field facilities.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Underground storage... of the Natural Gas Act for Certain Transactions and Abandonment § 157.213 Underground storage field... operate facilities for the remediation and maintenance of an existing underground storage...

  7. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    This document, Volume 6 Book 2, contains design studies for a Monitored Retrievable Storage (MRS) Facility. Topics discussed include: materials handling; processing; support systems; support utilities; spent fuel; high-level radioactive wastes and storage; field drywell storage; ALARA consideration; safety considerations; and design approach

  8. 303-K Radioactive mixed-waste storage facility closure plan

    International Nuclear Information System (INIS)

    The Hanford Site, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 303-K Radioactive Mixed-Waste Storage Facility (303-K Facility) has been used since 1943 to store various radioactive and dangerous process materials and wastes generated by the fuel manufacturing processes in the 300 Area. The 303-K Radioactive Mixed-Waste Storage Facility is used for the storage of mixed wastes. The north end of the building was used for containers of liquid waste and the outside storage areas were used for containers of solid waste. From 1977 to 1982, the north room was used to cure concreted billets of recyclable scrap uranium with Zircaloy-2 and copper silicon alloy chips and fines. The concretion process was discontinued in 1982, and these materials are now calcinated in the 303-M Oxide Facility. Other drummed materials have been stored on outside storage areas near the 303-K Facility on concrete, asphalt, and gravel pads. The 303-K Facility will be closed as defined in the Resource Conservation and Recovery Act of 1976 (RCRA). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 303-K Facility as a greater that 90-day storage facility. Clean closure of the 303-K Building and associated storage areas is the proposed method for final closure of the facility. After this facility is clean closed, it will be used for the storage of radioactive mixed waste for less than 90 days. 15 refs., 14 figs., 4 tabs

  9. Radiation analysis for a generic centralized interim storage facility

    International Nuclear Information System (INIS)

    This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required

  10. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  11. Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A

    International Nuclear Information System (INIS)

    This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification

  12. 303-K Storage Facility: Report on FY98 closure activities

    International Nuclear Information System (INIS)

    This report summarizes and evaluates the decontamination activities, sampling activities, and sample analysis performed in support of the closure of the 303-K Storage Facility. The evaluation is based on the validated data included in the data validation package (98-EAP-346) for the 303-K Storage Facility. The results of this evaluation will be used for assessing contamination for the purpose of closing the 303-K Storage Facility as described in the 303-K Storage Facility Closure Plan, DOE/RL-90-04. The closure strategy for the 303-K Storage Facility is to decontaminate the interior of the north half of the 303-K Building to remove known or suspected dangerous waste contamination, to sample the interior concrete and exterior soils for the constituents of concern, and then to perform data analysis, with an evaluation to determine if the closure activities and data meet the closure criteria. The closure criteria for the 303-K Storage Facility is that the concentrations of constituents of concern are not present above the cleanup levels. Based on the evaluation of the decontamination activities, sampling activities, and sample data, determination has been made that the soils at the 303-K Storage Facility meet the cleanup performance standards (WMH 1997) and can be clean closed. The evaluation determined that the 303-K Building cannot be clean closed without additional closure activities. An additional evaluation will be needed to determine the specific activities required to clean close the 303-K Storage Facility. The radiological contamination at the 303-K Storage Facility is not addressed by the closure strategy

  13. 303-K Storage Facility report on FY98 closure activities

    Energy Technology Data Exchange (ETDEWEB)

    Adler, J.G.

    1998-07-17

    This report summarizes and evaluates the decontamination activities, sampling activities, and sample analysis performed in support of the closure of the 303-K Storage Facility. The evaluation is based on the validated data included in the data validation package (98-EAP-346) for the 303-K Storage Facility. The results of this evaluation will be used for assessing contamination for the purpose of closing the 303-K Storage Facility as described in the 303-K Storage Facility Closure Plan, DOE/RL-90-04. The closure strategy for the 303-K Storage Facility is to decontaminate the interior of the north half of the 303-K Building to remove known or suspected dangerous waste contamination, to sample the interior concrete and exterior soils for the constituents of concern, and then to perform data analysis, with an evaluation to determine if the closure activities and data meet the closure criteria. The closure criteria for the 303-K Storage Facility is that the concentrations of constituents of concern are not present above the cleanup levels. Based on the evaluation of the decontamination activities, sampling activities, and sample data, determination has been made that the soils at the 303-K Storage Facility meet the cleanup performance standards (WMH 1997) and can be clean closed. The evaluation determined that the 303-K Building cannot be clean closed without additional closure activities. An additional evaluation will be needed to determine the specific activities required to clean close the 303-K Storage Facility. The radiological contamination at the 303-K Storage Facility is not addressed by the closure strategy.

  14. Conceptual design report, Sodium Storage Facility, Fast Flux Test Facility, Project F-031

    International Nuclear Information System (INIS)

    The Sodium Storage Facility Conceptual Design Report provides conceptual design for construction of a new facility for storage of the 260,000 gallons of sodium presently in the FFTF plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium

  15. Structural Integrity Program for INTEC Calcined Solids Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeffrey Bryant

    2008-08-30

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities.

  16. Technical Safety Requirements for the Waste Storage Facilities May 2014

    International Nuclear Information System (INIS)

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  17. Technical Safety Requirements for the Waste Storage Facilities May 2014

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-04-16

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  18. Wet spent fuel interim storage facility

    International Nuclear Information System (INIS)

    The article deals with the Spent Fuel Complementary Storage Unit, which was designed for the Almirante Alvaro Alberto Nuclear Power Station situated near Rio de Janeiro. The aim of the article is to present the technical solution of complementary storage. The design deals with different reactor technologies made by Areva and Westinghouse. The article also deals with the technically interesting solution of the storage tank heat removal and its dimensioning. (author)

  19. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

  20. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

  1. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D T

    2010-03-05

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

  2. The interim storage facility with dry storage casks and its safeguards activity

    International Nuclear Information System (INIS)

    Recyclable-Fuel Storage Company (RFS) is constructing an interim storage facility of spent fuel at Recyclable-Fuel Storage Center (RFSC) in Aomori Prefecture. Metallic dry casks are employed to contain the spent fuel from nuclear power plants and to serve for about 50 years in RFSC. Metallic dry casks have already been used for dry cask storage facility at Tokai No.2 power station of Japan Atomic Power Company. But, RFSC is not exactly the same as the dry cask storage facility at Tokai No.2 power station, for example, cask transportation between facilities and no hot cells. Therefore, additional safeguards activities are necessary. The outline of the design and handling of metallic dry casks at RFSC and the currently developing status of safeguards activity such as containment and surveillance for the cask receipt and storage at RFSC, etc are described. (author)

  3. MRI device – alternative for electrical energy storage

    Directory of Open Access Journals (Sweden)

    Molokáč, Š.

    2008-01-01

    Full Text Available It is well known, that the electrical energy storage in the large scale is basically difficult process. Such a process is marked by the energy losses, as the conversion of electrical energy into another form, is most frequently for example mechanical, and then back to the primary electrical form. Though, the superconducting magnetic energy storage (SMES technology offers the energy storage in an unchanged form, which is advantageous primarily in the achieved efficiency. Magnetic resonance imaging (MRI devices, commonly used in the medical facilities are based on the application of superconducting magnet. After its rejection from operation, there is possibility of using such devices for energy storage purposes. Additionally, such a technology of storage is also ecological.

  4. Safety analysis report for the Waste Storage Facility. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  5. 190-C Facility <90 Day Storage Pad inspection plan

    International Nuclear Information System (INIS)

    This document provides the inspection plan for the 190-C Facility <90 Day Storage Pad. The 190-C Facility <90 Day Storage Pad stores waste oils contaminated with lead generated while draining oil from equipment within 290-C. The 190-C pumphouse originally pumped water to the C Reactor after the water was treated/filtered in an adjacent building. Characteristic waste oil is removed from the facility equipment, packaged and stored in fifty-five-gallon drums. Included in this plan are the details concerning necessary security equipment, inspection for proper sign posting and other factors that may affect the integrity of the facility. The 190-C Facility <90 Day Storage Pad shall be inspected at lease once each calendar week

  6. Documented Safety Analysis for the Waste Storage Facilities March 2010

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D T

    2010-03-05

    This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

  7. Hazard categorization and classification for the sodium storage facility

    International Nuclear Information System (INIS)

    The Sodium Storage Facility is planned to be constructed in the 400 area for long term storage of sodium from the Fast Flux Test Facility (FFTF). It will contain four large sodium storage tanks. Three of the tanks have a capacity of 80,000 gallons of sodium each, and the fourth will hold 52,500 gallons. The tanks will be connected by piping with each other and to the FFTF. Sodium from the FFTF primary and secondary Heat Transport Systems (HTS), Interim Decay Storage (IDS), and the Fuel Storage Facility (FSF) will be transferred to the facility, and stored there in a frozen state pending final disposition. A Hazard Classification has been performed in order to evaluate the potential toxic consequences of a sodium fire according to the provisions of DOE Order 5481.1B. The conclusion of these evaluations is that the Sodium Storage Facility meets the requirements of the lowest Hazard Category, i.e., radiological facility, and the Hazard Classification is recommended to be moderate

  8. Documented Safety Analysis for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D

    2008-06-16

    This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

  9. Staging and storage facility feasibility study. Final report

    International Nuclear Information System (INIS)

    This study was performed to investigate the feasibility of adapting the design of the HWVP Canister Storage Building (CSB) to meet the needs of the WHC Spent Nuclear Fuel Project for Staging and Storage Facility (SSF), and to develop Rough Order of Magnitude (ROM) cost and schedule estimates

  10. On-site intermediate storage facilities in Germany

    International Nuclear Information System (INIS)

    Full text: In 2002 German utilities and the federal government agreed on the future of nuclear power in Germany. Part of this 'consensus' are site specific phase out periods, termination of reprocessing and the erection of on-site storage facilities. Shipment of spent fuel to reprocessing plants is only allowed until 2005, shipments to the German joint storage facilities of Ahaus and Gorleben have to be minimized. Each nuclear power plant has to create its own spent fuel storage with appropriate capacity. The necessary storage capacity is about 20 to 40 t/a and per plant, corresponding to 40 to 80 PWR- and 140 to 180 BWR-fuel bundles, depending on plant power and discharge burnup. Wet storage capacity inside the reactor building of most German NPPs was increased (compact storage) when shipments of spent fuel were ceased, following discussions about surface contaminations on casks. To avoid shut-down some plants even built short term storage facilities. Whereas short-term storage is to guarantee undisturbed operation of plants on an intermediate time scale, long term storage - until final nuclear waste disposal after 2030 is available - is also driven by economical considerations. Of the existing storage techniques wet and dry storage were analyzed with respect to costs and time for design, licensing and construction. Both techniques fulfill the safety requirements, but wet storage turns out to be more costly because of the necessary heat removing devices and operating expense. Total costs for construction, operation and decommissioning of a wet storage facility - as it was built in Obrigheim in 1998 on a smaller scale - rank from 80 to 250 million Euro, 1,4 million Euro annually and 45 million Euro for decommissioning (price index of 2003), respectively. Compared to that, dry storage needs about 26 million Euro for construction, annually 0,3 million Euro plus 2 - 3 casks (e.g. of the CASTOR type) with around 1,2 million Euro per flask and about 12 million Euro for

  11. Environmental assessment for the construction and operation of waste storage facilities at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    DOE is proposing to construct and operate 3 waste storage facilities (one 42,000 ft{sup 2} waste storage facility for RCRA waste, one 42,000 ft{sup 2} waste storage facility for toxic waste (TSCA), and one 200,000 ft{sup 2} mixed (hazardous/radioactive) waste storage facility) at Paducah. This environmental assessment compares impacts of this proposed action with those of continuing present practices aof of using alternative locations. It is found that the construction, operation, and ultimate closure of the proposed waste storage facilities would not significantly affect the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

  12. Waste Encapsulation and Storage Facility (WESF) Hazards Assessment

    International Nuclear Information System (INIS)

    This report documents the hazards assessment for the Waste Encapsulation and Storage Facility (WESF) located on the U.S. Department of Energy (DOE) Hanford Site. This hazards assessment was conducted to provide the emergency planning technical basis for WESF. DOE Orders require an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification

  13. Automation in a material processing/storage facility

    International Nuclear Information System (INIS)

    The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, therefore, be accomplished in a rational and disciplined manner to satisfy the strict operational requirements of the facility. Among the functions to be automated are the transport of containers between process and storage areas via an Automatic Guided Vehicle (AGV), and various processes in the Shipping Package Unpackaging (SPU) area, the Accountability Measurements (AM) area, the Special Isotope Storage (SIS) vault and the Special Nuclear Materials (SNM) vault. Other areas of the facility are also being automated, but are outside the scope of this paper

  14. Final safety analysis report for the irradiated fuels storage facility

    International Nuclear Information System (INIS)

    A fuel storage facility has been constructed at the Idaho Chemical Processing Plant to provide safe storage for spent fuel from two commercial HTGR's, Fort St. Vrain and Peach Bottom, and from the Rover nuclear rocket program. The new facility was built as an addition to the existing fuel storage basin building to make maximum use of existing facilities and equipment. The completed facility provides dry storage for one core of Peach Bottom fuel (804 elements), 11/2 cores of Fort St. Vrain fuel (2200 elements), and the irradiated fuel from the 20 reactors in the Rover program. The facility is designed to permit future expansion at a minimum cost should additional storage space for graphite-type fuels be required. A thorough study of the potential hazards associated with the Irradiated Fuels Storage Facility has been completed, indicating that the facility is capable of withstanding all credible combinations of internal accidents and pertinent natural forces, including design basis natural phenomena of a 10,000 year flood, a 175-mph tornado, or an earthquake having a bedrock acceleration of 0.33 g and an amplification factor of 1.3, without a loss of integrity or a significant release of radioactive materials. The design basis accident (DBA) postulated for the facility is a complete loss of cooling air, even though the occurrence of this situation is extremely remote, considering the availability of backup and spare fans and emergency power. The occurrence of the DBA presents neither a radiation nor an activity release hazard. A loss of coolant has no effect upon the fuel or the facility other than resulting in a gradual and constant temperature increase of the stored fuel. The temperature increase is gradual enough that ample time (28 hours minimum) is available for corrective action before an arbitrarily imposed maximum fuel centerline temperature of 11000F is reached

  15. Hanford Site existing irradiated fuel storage facilities description

    Energy Technology Data Exchange (ETDEWEB)

    Willis, W.L.

    1995-01-11

    This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

  16. 303-K Storage Facility closure plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-15

    Recyclable scrap uranium with zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/zircaloy-2 alloy, and zircaloy-2 chips and fines were secured in concrete billets (7.5-gallon containers) in the 303-K Storage Facility, located in the 300 Area. The beryllium/zircaloy-2 alloy and zircaloy-2 chips and fines are designated as mixed waste with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 303-K Storage Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act (RCRA) of 1976 and the Washington Administrative Code (WAC) Dangerous Waste Regulations, WAC 173-303-040. This closure plan presents a description of the 303-K Storage Facility, the history of materials and waste managed, and the procedures that will be followed to close the 303-K Storage Facility. The 303-K Storage Facility is located within the 300-FF-3 (source) and 300-FF-5 (groundwater) operable units, as designated in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992). Contamination in the operable units 300-FF-3 and 300-FF-5 is scheduled to be addressed through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 remedial action process. Therefore, all soil remedial action at the 304 Facility will be conducted as part of the CERCLA remedial action of operable units 300-FF-3 and 300-FF-5.

  17. Dry-type radioactive material storage facility

    International Nuclear Information System (INIS)

    A plurality of container tubes containing a plurality of canisters therein are disposed in a canister storage chamber. High level radioactive materials are filled in the canisters in the form of glass solidification materials. The canister storage chamber is divided into two cooling channels by a horizontal partition wall. Each of the container tubes is suspended from a ceiling slab and pass through the horizontal partition wall. Namely, each of the container tubes vertically traverses the cooling channel formed between the ceiling slab and the partition wall and extends to the cooling channel formed between the partition wall and a floor slab. Cooling gases heated in the cooling channel below the partition wall are suppressed from rising to the cooling channel above the partition wall. Therefore, the container tubes are efficiently cooled even in a cooling channel above the partition wall to unify temperature distribution in the axial direction of the container tubes. (I.N.)

  18. Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the U.S. Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE's Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE's 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases

  19. Information related to low-level mixed waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    This report was prepared to support the analysis of risks and costs associated with the proposed treatment of low-level mixed waste (LLMW) under management of the US Department of Energy (DOE). The various waste management alternatives for treatment of LLMW have been defined in the DOE's Office of Waste Management Programmatic Environmental Impact Statement. This technical memorandum estimates the waste material throughput expected at each proposed LLMW treatment facility and analyzes potential radiological and chemical releases at each DOE site resulting from treatment of these wastes. Models have been developed to generate site-dependent radiological profiles and waste-stream-dependent chemical profiles for these wastes. Current site-dependent inventories and estimates for future generation of LLMW have been obtained from DOE's 1994 Mixed Waste Inventory Report (MWIR-2). Using treatment procedures developed by the Mixed Waste Treatment Project, the MWIR-2 database was analyzed to provide waste throughput and emission estimates for each of the different waste types assessed in this report. Uncertainties in the estimates at each site are discussed for waste material throughputs and radiological and chemical releases

  20. Conceptual design for concrete storage cask and landscape design of its storage facility

    International Nuclear Information System (INIS)

    As an advantageous interim spent fuel dry storage system at a reactor site, the conceptual study of the vertical dry cask spent fuel storage system and the landscape evaluation of the facility are carried out. The system is concluded to be viable means for the spent fuel storage and landscape design is confirmed to be necessary for environment conservation and for avoiding the damage of a natural grand view. (author)

  1. INEEL special case waste storage and disposal alternatives

    Energy Technology Data Exchange (ETDEWEB)

    Larson, L.A.; Bishop, C.W.; Bhatt, R.N.

    1997-07-01

    Special case waste is historically defined as radioactive waste that does not have a path forward or fit into current Department of Energy management plans for final treatment or disposal. The objectives of this report, relative to special case waste at the Idaho National Engineering and Environmental Laboratory, are to (a) identify its current storage locations, conditions, and configuration; (b) review and verify the currently reported inventory; (c) segregate the inventory into manageable categories; (d) identify the portion that has a path forward or is managed under other major programs/projects; (e) identify options for reconfiguring and separating the disposable portions; (f) determine if the special case waste needs to be consolidated into a single storage location; and (g) identify a preferred facility for storage. This report also provides an inventory of stored sealed sources that are potentially greater than Class C or special case waste based on Nuclear Regulatory Commission and Site-Specific Waste Acceptance Criteria.

  2. The interim storage facility at the Beznau nuclear power plant

    International Nuclear Information System (INIS)

    In Switzerland, the nuclear power plants (NPPs) are responsible for storage of their own wastes. In addition to the centralised ZWILAG facility at Wuerenlingen, which is planned jointly by the five operating plants, each NPP has its own on-site storage capacity. The example considered in this article is the interim storage facility at the Beznau power plant. At Beznau, the first stage of the ZWIBEZ project involved the opening of a store for low-level waste in March 1993. Future stages will provide additional capacity for intermediate-level and high-level wastes (and spent fuel elements). The store for intermediate-level waste will not be constructed, provided there is no further delay in the realisation of the ZWILAG facility. (author) 5 figs., 1 tab

  3. 303-K Storage facility sampling and analysis plan

    Energy Technology Data Exchange (ETDEWEB)

    Adler, J.G.

    1997-07-01

    This document describes the cleanup, sampling, and analysis activities associated with the closure of the 303-K Storage Facility under the Washington Administrative Code (WAC) 173-303-610, ``Dangerous Waste Regulations.`` this document is a supplement to the 303-K Storage Facility Closure Plan (DOE-RL 1995a) (Closure Plan). The objective of these activities is to support clean closure of the 303 K Storage Facility. This document defines the information and activities needed to meet this objective, including: constituents of concern, cleanup performance standards, cleanup activities, sampling locations and methods, field screening locations and methods, field quality control requirements, laboratory analytical methods, and data validation methodology. This document supersedes the Closure Plan if the two conflict

  4. Inventory extension at the Nuclear Materials Storage Facility

    International Nuclear Information System (INIS)

    The planned renovation of the Nuclear Material Storage Facility (NMSF) at Los Alamos National Laboratory will be a significant addition to the plutonium storage capacity of the nuclear weapons complex. However, the utility of the facility may be impaired by an overly conservative approach to performing inventories of material in storage. This report examines options for taking advantage of provisions in Department of Energy orders to extend the time between inventories. These extensions are based on a combination of modern surveillance technology, facility design features, and revised operational procedures. The report also addresses the possibility that NMSF could be the site of some form of international inspection as part of the US arms control and nonproliferation policy

  5. Dry spent fuel storage facility at Kozloduy Nuclear Power Plant

    International Nuclear Information System (INIS)

    The Dry Spent Fuel Storage Facility (DSF) is financed by the Kozloduy International Decommissioning Support Fund (KIDSF) which is managed by European Bank for Reconstruction and Development (EBRD). On behalf of the Employer, the Kozloduy Nuclear Power Plant, a Project Management Unit (KPMU) under lead of British Nuclear Group is managing the contract with a Joint Venture Consortium under lead of RWE NUKEM mbH. The scope of the contract includes design, manufacturing and construction, testing and commissioning of the new storage facility for 2800 VVER-440 spent fuel assemblies at the KNPP site (turn-key contract). The storage technology will be cask storage of CONSTOR type, a steel-concrete-steel container. The licensing process complies with the national Bulgarian regulations and international rules. (authors)

  6. Heat removal system of dry storage facility for spent fuel

    International Nuclear Information System (INIS)

    Dry vault type and concrete cask type are two of the interim dry storage systems on which future expections are being placed because of the natural convection air cooling system that requires no active systems and generates little radioactive waste. Maximum allowable temperature of fuel cladding was decided based on creep strain criteria for long term dry storage environment to avoid cladding degradation. It was necessary to establish an evaluation method of heat transfer inside and outside the fuel loaded canisters for the design of the storage facility. We carried out the heat transfer tests and the analytical study taking notice of the behavior of thermal convection in a canister for the designing of the spent fuel dry storage facility. (author)

  7. Hanford facility dangerous waste permit application, PUREX storage tunnels

    Energy Technology Data Exchange (ETDEWEB)

    Haas, C. R.

    1997-09-08

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, `operating` treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24).

  8. Safety and Licensing of Spent Fuel Storage Facilities

    International Nuclear Information System (INIS)

    All operating nuclear power reactors in the United States (U.S.) are storing spent fuel on-site in spent fuel pools licensed by the U.S. Nuclear Regulatory Commission (NRC). Spent fuel pools at U.S. reactors were not designed to store the full amount of spent fuel generated during the lifetime of plant operation. Consequently, most utilities expanded their storage capacity by the use of high-density storage racks. Even with the high density racks, most utilities will need additional storage capacity. When it became apparent that nuclear power plants were going to need additional spent fuel storage space, the NRC amended its regulations in 1980 to provide nuclear power plants with alternate spent fuel storage in an independent spent fuel storage installation (ISFSI). NRC provides for a 20-year specific license with the option to renew the license for additional 20-year terms. In 1990, the NRC implemented the General License option to ease the burden on nuclear power plants that have a license to either operate or possess fuel. The general license for each storage cask terminates 20 years after the storage cask is first used by the licensee. The first storage cask using a general license was loaded in 1994. This paper discusses NRC experiences and its knowledge gained in licensing over the past 30 years and renewing the licenses for three ISFSIs and how this knowledge has driven the NRC to revise its guidance and thought processes for dry storage. (author)

  9. Fuel Storage Facility Final Safety Analysis Report. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Linderoth, C.E.

    1984-03-01

    The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

  10. Waste Encapsulation and Storage Facility mission analysis report

    International Nuclear Information System (INIS)

    This report defines the mission for the Waste Encapsulation and Storage Facility (WESF). It contains summary information regarding the mission analysis which was performed by holding workshops attended by relevant persons involved in the WESF operations. The scope of the WESF mission is to provide storage of Cesium (Cs) and Strontium (Sr) capsules, previously produced at WESF, until every capsule has been removed from the facility either to another storage location, for disposal or for beneficial use by public or private enterprises. Since the disposition of the capsules has not yet been determined, they may be stored at WESF for many years, even decades. The current condition of the WESF facility must be upgraded and maintained to provide for storage which is safe, cost effective, and fully compliant with DOE direction as well as federal, state, and local laws and regulations. The Cs capsules produced at WESF were originally released to private enterprises for uses such as the sterilization of medical equipment; but because of the leakage of one capsule, all are being returned. The systems, subsystems, and equipment not required for the storage mission will be available for use by other projects or private enterprises. Beyond the storage of the Cs and Sr capsules, no future mission for the WESF has been identified

  11. Conceptual design study of a concrete canister spent-fuel storage facility

    International Nuclear Information System (INIS)

    This report presents a conceptual design study for the interim storage of CANDU spent fuel in concrete canisters. The canisters will be concrete flasks, which contain fuel prepackaged in double steel containment, and will be cooled by natural air convection. This is one of the methods proposed as a potential alternative to water pool storage. A preliminary study of this concept was done by CAFS (Committee Assessing Fuel Storage), and WNRE (Whiteshell Nuclear Research Establishment) is currently conducting a development and demonstration program. This study of a central facility for the storage of all Canadian spent fuel arisings to the year 2000 was completed in 1975. A brief description of the facilities required and the operations involved, a summary of costs, a survey of the monitoring requirements and a prediction of the personnel exposures associated with this method of storing spent fuel are reported here. The estimated total cost of interim storage in cylindrical canisters at a central site is $6.02/kg U (1975 dollars). Approximately half of this cost is incurred in the shipment of fuel from the reactors to the storage facility. (author)

  12. Safety concept for interim storage facilities in Fukushima

    International Nuclear Information System (INIS)

    The Ministry of the Environment is planning to construct the Interim Storage Facility for soil and waste generated in Fukushima prefecture, due to the accident of Fukushima Daiichi Nuclear Power Plant. This paper describes the result of study for the safety concepts. Concrete components are estimation of soil/waste generation, soil characterization, structure and location of facilities, radioactive safety assessment, operational management, approach for transportation concept, basic principle of environmental conservation measures. (author)

  13. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed

  14. Dry storage facility at Kozloduy Nuclear Power Plant

    International Nuclear Information System (INIS)

    The Kozloduy Nuclear Power Plant (KNPP) is located in the north-west of Bulgaria beside the River Danube. There are 6 reactors, all of Russian design, that were commissioned between 1974 and 1991. The first 4 VVER-440 units were finally shut down by the end of 2006 and are now being decommissioned. The 2 later VVER-1000 reactors are still operating. The construction of a dry spent fuel storage facility (DSF) was a necessary measure required to comply with the national strategy for spent fuel and radioactive waste management, approved by the Bulgarian Government. This facility should be designed to receive spent irradiated nuclear fuel from the 6 reactor units at KNPP. Such a facility allows sufficient time to decide whether spent fuel should be reprocessed or destined for direct disposal. In May 2004 the KNPP awarded a contract to a Consortium comprising the 2 German companies NUKEM Technologies GmbH and GNS Gesellschaft fuer Nuklear-Service mbH for the design and erection of a dry spent fuel storage facility. The storage facility was finished and accepted by the Client in March 2011. The operation of the facility will start after reception of the respective license granted by the Competent Authorities. (orig.)

  15. Dry storage facility at Kozloduy Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Botzem, Werner; Graham, Andrew [NUKEM Technologies GmbH, Alzenau (Germany); Kuehne, Bernhard; Schulte, Matthias [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

    2011-04-15

    The Kozloduy Nuclear Power Plant (KNPP) is located in the north-west of Bulgaria beside the River Danube. There are 6 reactors, all of Russian design, that were commissioned between 1974 and 1991. The first 4 VVER-440 units were finally shut down by the end of 2006 and are now being decommissioned. The 2 later VVER-1000 reactors are still operating. The construction of a dry spent fuel storage facility (DSF) was a necessary measure required to comply with the national strategy for spent fuel and radioactive waste management, approved by the Bulgarian Government. This facility should be designed to receive spent irradiated nuclear fuel from the 6 reactor units at KNPP. Such a facility allows sufficient time to decide whether spent fuel should be reprocessed or destined for direct disposal. In May 2004 the KNPP awarded a contract to a Consortium comprising the 2 German companies NUKEM Technologies GmbH and GNS Gesellschaft fuer Nuklear-Service mbH for the design and erection of a dry spent fuel storage facility. The storage facility was finished and accepted by the Client in March 2011. The operation of the facility will start after reception of the respective license granted by the Competent Authorities. (orig.)

  16. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    International Nuclear Information System (INIS)

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11

  17. Introducing Systematic Aging Management for Interim Storage Facilities in Germany

    International Nuclear Information System (INIS)

    In Germany twelve at-reactor and three central (away from reactor) dry storage facilities are in operation, where the fuel is stored in combined transport-and-storage casks. The safety of the storage casks and facilities has been approved and is licensed for up to 40 years operating time. If the availability of a final disposal facility for the stored wastes (spent fuel and high-level wastes from reprocessing) will be further delayed the renewal of the licenses can become necessary in future. Since 2001 Germany had a regulatory guideline for at-reactor dry interim storage of spent fuel. In this guideline some elements of ageing were implemented, but no systematic approach was made for a state-of-the-art ageing management. Currently the guideline is updated to include all kind of storage facilities (central storages as well) and all kinds of high level waste (also waste from reprocessing). Draft versions of the update are under discussion. In these drafts a systematic ageing management is seen as an instrument to upgrade the available technical knowledge base for possible later regulatory decisions, should it be necessary to prolong storage periods to beyond the currently approved limits. It is further recognized as an instrument to prevent from possible and currently unrecognized ageing mechanisms. The generation of information on ageing can be an important basis for the necessary safety-relevant verifications for long term storage. For the first time, the demands for a systematic monitoring of ageing processes for all safety-related components of the storage system are described. In addition, for inaccessible container components such as the seal system, the neutron shielding, the baskets and the waste inventory, the development of a monitoring program is recommended. The working draft to the revised guideline also contains recommendations on non-technical ageing issues such as the long-term preservation of knowledge, long term personnel planning and long term

  18. Financing strategic healthcare facilities: the growing attraction of alternative capital.

    Science.gov (United States)

    Zismer, Daniel K; Fox, James; Torgerson, Paul

    2013-05-01

    Community health system leaders often dismiss use of alternative capital to finance strategic facilities as being too expensive and less strategically useful, preferring to follow historical precedent and use tax-exempt bonding to finance such facilities. Proposed changes in accounting rules should cause third-party-financed facility lease arrangements to be treated similarly to tax-exempt debt financings with respect to the income statement and balance sheet, increasing their appeal to community health systems. An in-depth comparison of the total costs associated with each financing approach can help inform the choice of financing approaches by illuminating their respective advantages and disadvantages. PMID:23678696

  19. Treatment, storage, and disposal alternatives for the gunite and associated tanks at the Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The gunite and associated tanks (GAAT) are inactive, liquid low-level waste tanks located in and around the North and South Tank Farms at Oak Ridge National Laboratory. These underground tanks are the subject of an ongoing treatability study that will determine the best remediation alternatives for the tanks. As part of the treatability study, an assessment of viable treatment, storage, and disposal (TSD) alternatives has been conducted. The report summarizes relevant waste characterization data and statistics obtained to date. The report describes screening and evaluation criteria for evaluating TSD options. Individual options that pass the screening criteria are described in some detail. Order-or-magnitude cost estimates are presented for each of the TSD system alternatives. All alternatives are compared to the baseline approach of pumping all of the GAAT sludge and supernate to the Melton Valley Storage Tank (MVST) facility for eventual TSD along with the existing MOST waste. Four TSD systems are identified as alternatives to the baseline approach. The baseline is the most expensive of the five identified alternatives. The least expensive alternative is in-situ grouting of all GAAT sludge followed by in-situ disposal. The other alternatives are: (1) ex-situ grouting with on-site storage and disposal at Nevada Test Site (NTS); (2) ex-situ grouting with on-site storage and disposal at NTS and the Waste Isolation Pilot Plant (WIPP); and (3) ex-situ vitrification with on-site storage and disposal at NTS and WIPP

  20. Operations and Maintenance Concept Plan for the Immobilized High-Level Waste (IHLW) Interim Storage Facility

    International Nuclear Information System (INIS)

    This OandM Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design

  1. The GreenLab Research Facility: A Micro-Grid Integrating Production, Consumption and Storage of Clean Energy

    Science.gov (United States)

    McDowell Bomani, Bilal Mark; Elbuluk, Malik; Fain, Henry; Kankam, Mark D.

    2012-01-01

    There is a large gap between the production and demand for energy from alternative fuel and alternative renewable energy sources. The NASA Glenn Research Center (GRC) has initiated a laboratory-pilot study that concentrates on using biofuels as viable alternative fuel resources for the field of aviation, as well as, utilizing wind and solar technologies as alternative renewable energy resources, and in addition, the use of pumped water for storage of energy that can be retrieved through hydroelectric generation. This paper describes the GreenLab Research Facility and its power and energy sources with .recommendations for worldwide expansion and adoption of the concept of such a facility

  2. Transuranic storage and assay facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    Porten, D.R., Fluor Daniel Hanford

    1997-02-12

    The Transuranic Waste Storage and Assay Facility (TRUSAF) Interim Safety Basis document provides the authorization basis for the interim operation and restriction on interim operations for the TRUSAF. The TRUSAF ISB demonstrates that the TRUSAF can be operated safely, protecting the workers, the public, and the environment. The previous safety analysis document TRUSAF Hazards Identification and Evaluation (WHC 1987) is superseded by this document.

  3. Commercial experience with facility deactivation to safe storage

    Energy Technology Data Exchange (ETDEWEB)

    Sype, T.T. [Sandia National Labs., Albuquerque, NM (United States); Fischer, S.R. [Los Alamos National Lab., NM (United States); Lee, J.H. Jr.; Sanchez, L.C.; Ottinger, C.A.; Pirtle, G.J. [Sandia National Labs., Albuquerque, NM (United States)

    1995-09-01

    The Department of Energy (DOE) has shutdown many production reactors; the Department has begun a major effort to also shutdown a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe- storage status, i.e., deactivation, before conducting decommissioning- for perhaps as long as 20 years. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons-learned study of commercial experience with safe storage and decommissioning. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this document can provide insight into transitioning challenges that Will be faced by the DOE weapons complex.

  4. Commercial experience with facility deactivation to safe storage

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has shutdown many production reactors; the Department has begun a major effort to also shutdown a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe- storage status, i.e., deactivation, before conducting decommissioning- for perhaps as long as 20 years. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons-learned study of commercial experience with safe storage and decommissioning. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this document can provide insight into transitioning challenges that Will be faced by the DOE weapons complex

  5. Modular Energy Storage System for Alternative Energy Vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, Janice [Magna Electronics Inc., Auburn Hills, MI (United States); Ervin, Frank [Magna Electronics Inc., Auburn Hills, MI (United States)

    2012-05-15

    An electrical vehicle environment was established to promote research and technology development in the area of high power energy management. The project incorporates a topology that permits parallel development of an alternative energy delivery system and an energy storage system. The objective of the project is to develop technologies, specifically power electronics, energy storage electronics and controls that provide efficient and effective energy management between electrically powered devices in alternative energy vehicles plugin electric vehicles, hybrid vehicles, range extended vehicles, and hydrogen-based fuel cell vehicles. In order to meet the project objectives, the Vehicle Energy Management System (VEMS) was defined and subsystem requirements were obtained. Afterwards, power electronics, energy storage electronics and controls were designed. Finally, these subsystems were built, tested individually, and integrated into an electric vehicle system to evaluate and optimize the subsystems performance. Phase 1 of the program established the fundamental test bed to support development of an electrical environment ideal for fuel cell application and the mitigation of many shortcomings of current fuel cell technology. Phase 2, continued development from Phase 1, focusing on implementing subsystem requirements, design and construction of the energy management subsystem, and the integration of this subsystem into the surrogate electric vehicle. Phase 2 also required the development of an Alternative Energy System (AES) capable of emulating electrical characteristics of fuel cells, battery, gen set, etc. Under the scope of the project, a boost converter that couples the alternate energy delivery system to the energy storage system was developed, constructed and tested. Modeling tools were utilized during the design process to optimize both component and system design. This model driven design process enabled an iterative process to track and evaluate the impact

  6. Hydrogen storage alternatives - a technological and economic assessment

    Energy Technology Data Exchange (ETDEWEB)

    Pettersson, Joakim; Hjortsberg, Ove [Volvo Teknisk Utveckling AB, Goeteborg (Sweden)

    1999-12-01

    This study reviews state-of-the-art of hydrogen storage alternatives for vehicles. We will also discuss the prospects and estimated cost for industrial production. The study is based on published literature and interviews with active researchers. Among the alternatives commercially available today, we suggest using a moderate-pressure chamber for seasonal stationary energy storage; metal hydride vessels for small stationary units; a roof of high-pressure cylinders for buses, trucks and ferries; cryogenic high-pressure vessels or methanol reformers for cars and tractors; and cryogenic moderate-pressure vessels for aeroplanes. Initial fuel dispensing systems should be designed to offer hydrogen in pressurised form for good fuel economy, but also as cryogenic liquid for occasional needs of extended driving range and as methanol for reformer-equipped vehicles. It is probable that hydrogen can be stored efficiently in adsorbents for use in recyclable hydrogen fuel containers or rechargeable hydrogen vessels operating at ambient temperature and possibly ambient pressure by year 2004, and at reasonable or even low cost by 2010. The most promising alternatives involve various forms of activated graphite nanostructures. Recommendations for further research and standardisation activities are given.

  7. Safeguards for spent nuclear fuel in transfer from wet storage to dry storage in on-site interim storage facilities

    International Nuclear Information System (INIS)

    Germany initially planned to store spent nuclear fuel in the two away-from-reactor interim storage facilities built at Ahaus and Gorleben. The current approach for spent fuel management is on-site interim storage in transport and storage casks as part of a political agreement between the German government and the nuclear operators on the future use of nuclear energy. A reason for this is to avoid near term transportation of spent fuel determined for direct final disposal via public road or rail systems to away-from-reactor storage facilities. Recent legislation has triggered the construction of 12 on-site dry storage facilities at nuclear power plants. Currently, such facilities are being taken into operation on a step-by-step basis. There is a strong need to develop acceptable safeguards concepts for both transfer and dry storage of spent fuel, ideally, a standard safeguards concept that would match all German nuclear power plant sites without ignoring technical and organisational differences. The paper will address the relevant issues and give an overview of the status of safeguards implementation. (author)

  8. Performance assessment of the proposed Monitored Retrievable Storage Facility

    International Nuclear Information System (INIS)

    Pacific Northwest laboratory (PNL) has completed a performance evaluation of the proposed monitored retrievable storage (MRS) facility. This study was undertaken as part of the Department of Energy MRS Program at PNL. The objective of the performance evaluation was to determine whether the conceptual MRS facility would be able to process spent fuel at the specified design rate of 3600 metric tons of uranium (MTU) per year. The performance of the proposed facility was assessed using the computer model COMPACT (Computer Optimization of Processing and Cask Transport) to simulate facility operations. The COMPACT model consisted of three application models each of which addressed a different aspect of the facility's operation: MRS/waste transportation interface; cask handling capability; and disassembly/consolidation (hot cell) operations. Our conclusions, based on the assessment of design criteria for the proposed facility, are as follows: Facilities and equipment throughout the facility have capability beyond the 3600 MTU/y design requirement. This added capability provides a reserve to compensate for unexpected perturbations in shipping or handling of the spent fuel. Calculations indicate that the facility's maximum maintainable processing capability is approximately 4800 MTU/y

  9. Inventory extension considerations for long-term storage at the nuclear materials storage facility

    International Nuclear Information System (INIS)

    Los Alamos National Laboratory is in the process of modifying its nuclear materials storage facility to a long-term storage configuration. In support of this effort, we examined technical and administrative means to extend periods between physical inventories. Both the frequency and sample size during a physical inventory could significantly impact required sizing of the non-destructive assay (NDA) laboratory as well as material handling capabilities. Several options are being considered, including (1) treating each storage location as a separate vault, (2) minimizing the number of items returned for quantitative analysis by optimizing the use of in situ confirmatory measurements, and (3) utilizing advanced monitoring technologies. Careful consideration of these parameters should allow us to achieve and demonstrate safe and secure storage while minimizing the impact on facility operations and without having to increase the size of the NDA laboratory beyond that required for anticipated shipping and receiving activities

  10. Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy waste management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    This report provides technical support information for use in analyzing environmental impacts associated with U.S. Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste-Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. 76 refs., 14 figs., 42 tabs

  11. Minimum criticality dose evaluation for the Irradiated Fuel Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, S.S. [Idaho National Engineering and Environmental Lab., ID (United States)

    1999-09-01

    The Irradiated Fuel Storage Facility (IFSF) is a government-owned, contractor-operated facility located at the Idaho National Engineering and Environmental Laboratory within the Idaho Nuclear Technology and Engineering Center. The mission of the facility is to provide safe dry storage for various types of irradiated fuels. Included are fuel elements such as irradiated ATR, EBR, MTR, Fort St. Vrain, TRIGA, and ROVER Parka fuels. Fuels requiring dry storage are received at the IFSF in fuel-shipping casks. At the facility receiving dock, the casks are removed from the transport vehicle, positioned in a cask transport car, and moved into the fuel-handling cave. Several functions are performed in the fuel-handling cave, including transferring fuel from shipping casks to storage canisters, preparing fuel elements for storage and processing. The minimum postulated criticality dose calculations were performed for the cask-receiving and fuel-handling areas to place criticality alarm system (CAS) detectors. The number of fissions for the minimum accident of concern is based on a dose of 20-rad air at 2 m in 1 min. The eigenvalue calculations were first performed to determine the size of the critical source. Then, two sets of fixed-source calculations were followed to calculate contributions from neutron and capture gamma rays and from prompt gamma rays. Two sets of MCNP calculations involved point and spherical critical sources. Validity of the Monte Carlo results was tested against ANISN deterministic calculations. The flux-to-dose conversion factors are based on ANSI/ANS-6.1.1-1977. All of the MCNP runs used continuous-energy ENDF/B-V cross sections. The BUGLE-80 cross-section library was used for the ANISN calculations.

  12. Minimum criticality dose evaluation for the Irradiated Fuel Storage Facility

    International Nuclear Information System (INIS)

    The Irradiated Fuel Storage Facility (IFSF) is a government-owned, contractor-operated facility located at the Idaho National Engineering and Environmental Laboratory within the Idaho Nuclear Technology and Engineering Center. The mission of the facility is to provide safe dry storage for various types of irradiated fuels. Included are fuel elements such as irradiated ATR, EBR, MTR, Fort St. Vrain, TRIGA, and ROVER Parka fuels. Fuels requiring dry storage are received at the IFSF in fuel-shipping casks. At the facility receiving dock, the casks are removed from the transport vehicle, positioned in a cask transport car, and moved into the fuel-handling cave. Several functions are performed in the fuel-handling cave, including transferring fuel from shipping casks to storage canisters, preparing fuel elements for storage and processing. The minimum postulated criticality dose calculations were performed for the cask-receiving and fuel-handling areas to place criticality alarm system (CAS) detectors. The number of fissions for the minimum accident of concern is based on a dose of 20-rad air at 2 m in 1 min. The eigenvalue calculations were first performed to determine the size of the critical source. Then, two sets of fixed-source calculations were followed to calculate contributions from neutron and capture gamma rays and from prompt gamma rays. Two sets of MCNP calculations involved point and spherical critical sources. Validity of the Monte Carlo results was tested against ANISN deterministic calculations. The flux-to-dose conversion factors are based on ANSI/ANS-6.1.1-1977. All of the MCNP runs used continuous-energy ENDF/B-V cross sections. The BUGLE-80 cross-section library was used for the ANISN calculations

  13. Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    This report provides technical support information for use in analyzing environmental impacts associated with US Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. Waste loads treated and disposed of for the LLW alternatives and subalternatives, or cases, addressed in the WM PEIS but not included in this report are presented in the Addendum

  14. Safeguards for spent nuclear fuel in transfer from wet storage to dry storage in on-site interim storage facilities

    International Nuclear Information System (INIS)

    Full text: In Germany, the current approach for spent fuel management is on-site interim storage in transport and storage casks as part of a political agreement between the German government and the nuclear operators on the future use of nuclear energy. Recent legislation has triggered the construction of on-site dry storage facilities at nuclear power plants. A reason behind this is to avoid transportation of spent fuel that is determined for direct final disposal via public road or rail systems to away-from-reactor storage facilities, as they had been built at Gorleben and Ahaus. Spent fuel will be loaded into shielding casks, e.g., of the CASTOR-type, and transferred out of the reactor containment into the associated on-site dry storage facility. On-site interim storage of spent nuclear fuel has a strong political relevance for the nuclear debate in Germany. On-site interim storage facilities are being taken into operation on a step-by-step basis. The intention is to develop acceptable safeguards concepts for both transfer and dry storage of spent fuel, ideally, a standard safeguards concept that would match all German nuclear power plant sites without ignoring technical and organisational differences. From the State's point of view the safeguards concepts have to comply with requirements related to operational safety, radiation protection, and physical protection. Furthermore, they have to take into account the political and technical boundary conditions as well as the time schedule for spent fuel transfers that has been coordinated between all the nuclear power plant operators. From a safeguards point of view material balance areas have to be defined and basic technical characteristics (design information) of the on-site interim storage facilities have to be reported to the Euratom Safeguards Office for re-transfer of this information to the International Atomic Energy Agency (IAEA). Furthermore, plant operators have to announce to Euratom, in advance, dates

  15. The dry storage cask in interim storage facility and safeguards activity

    International Nuclear Information System (INIS)

    The Japan Atomic Power Company (JAPC) is preparing for interim storage of spent fuel at Recyclable-Fuel Storage Center (RFSC) in Aomori Prefecture. Metallic dry casks are employed to contain the spent fuel and to serve for about 50 years in RFSC. Metallic dry casks have already been used for spent fuel dry storage at Tokai No.2 power station. But, RFSC is not exactly the same as the dry storage facility in Tokai No.2 power station, for example, casks are transported out side of the reactor site and RFSC has no fuel handling system. Therefore, additional implementation of safeguards is necessary. This report introduces the design and handling of metallic dry casks for RFSC and the currently developing status of the safeguards activity such as containment and surveillance for the fuel loading at the power station, the cask receipt and storage at RFSC, etc. (author)

  16. Greenfield Alternative Study LEU-Mo Fuel Fabrication Facility

    Energy Technology Data Exchange (ETDEWEB)

    Washington Division of URS

    2008-07-01

    This report provides the initial “first look” of the design of the Greenfield Alternative of the Fuel Fabrication Capability (FFC); a facility to be built at a Greenfield DOE National Laboratory site. The FFC is designed to fabricate LEU-Mo monolithic fuel for the 5 US High Performance Research Reactors (HPRRs). This report provides a pre-conceptual design of the site, facility, process and equipment systems of the FFC; along with a preliminary hazards evaluation, risk assessment as well as the ROM cost and schedule estimate.

  17. The interim fuel storage facility of the PBMR

    International Nuclear Information System (INIS)

    The PBMR's spent fuel and partially burnt fuel are stored in the sphere storage system (SSS), which acts as the interim fuel storage facility of the plant. It is unique in the world since the fuel is stored in bulk containers (called storage tanks), each capable of holding more than 500,000 spheres for a period of about 80 years. The SSS has the ability to transfer the contents of one tank to another tank, and to return partially burnt fuel back to the reactor core for re-fuelling. The storage tanks are individually sealed carbon steel pressure vessels. They form the final barrier of any fission products that have diffused from the fuel spheres. Sub-criticality is achieved through the geometric cross-section of the tank, and by taking credit for fuel burn-up. Protection from the corrosive environment where the PBMR Demonstration plant will be built is achieved by actively cooling the tank with clean dry air. In the event of an active cooling failure, louvres open automatically and cooling is done passively via natural convection making use of the chimney-effect. Sufficient radiation protection is provided around each tank to facilitate maintenance and inspection operations where needed. The design of the SSS is nearing the end of its basic design phase, and for some components, detail design work has already commenced. The design complies with all spent fuel storage requirements and is seen as a cost-effective solution for the interim storage of PBMR spent fuel

  18. 190-C Facility <90 Day Storage Pad training plan

    International Nuclear Information System (INIS)

    This is the Environmental Restoration Contractor (ERC) team training plan for the 190-C Facility <90 Day Storage Pad of Hazardous Waste. It is intended to meet the requirements of Washington Administrative Code (WAC) 173-303-330 and the Hanford Dangerous Waste Permit. Training unrelated to compliance with WAC 173-303-330 is not addressed in this training plan. WAC 173-303-330(1)(d)(ii, v, vi) requires that personnel be familiarized, where applicable, with waste feed cut-off systems, response to ground-water contamination incidents, and shutdown of operations. These are not applicable to 190-C Facility <90 Day Storage Pad, and are therefore not covered in this training plan

  19. 40 CFR 280.220 - Ownership of an underground storage tank or underground storage tank system or facility or...

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Ownership of an underground storage tank or underground storage tank system or facility or property on which an underground storage tank or underground storage tank system is located. 280.220 Section 280.220 Protection of Environment...

  20. Alternatives Generation Analysis Long Length Contaminated Equipment Removal System Storage

    International Nuclear Information System (INIS)

    Major pieces of Characterization sampling equipment are currently stored outdoors. This includes the Long Length Contaminated Equipment receiver trailer and transportation trailer. A decision is required to determine the preferred alternative for facilities to store and maintain this equipment. The Long Length Contaminated Equipment Removal System (LLCERS) consists of many tools, mechanisms, and controllers currently stored in various locations. Much of this equipment should be protected from the elements while being stored. Some of the LLCERS equipment should be protected with some kind of roof cover. This decision analysis is to determine the best alternative for weather protection for the large equipment requiring a cover. Additional details are included in Sections 2.0 and 5.0. Key assumptions used in this analysis are detailed in Section 3.2

  1. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

  2. INEL storage facility for sealed sources from the commercial sector

    International Nuclear Information System (INIS)

    Commercially owned sealed radiation sources determine by the US Nuclear Regulatory Commission to be a public health or safety hazard are accepted by the US Department of Energy, under the Atomic Energy Act of 1954, as material for reuse of recycle. To implement this policy, the sealed sources must be stored until proper disposition is determined. This report documents the investigation and selection process undertaken to locate a suitable storage facility at the Idaho National Engineering Laboratory

  3. Solid waste transuranic storage and assay facility indoor air sampling

    Energy Technology Data Exchange (ETDEWEB)

    Pingel, L.A., Westinghouse Hanford

    1996-08-20

    The purpose of the study is to collect and analyze samples of the indoor air at the Transuranic Storage and Assay Facility (TRUSAF), Westinghouse Hanford. A modified US EPA TO-14 methodology, using gas chromatography/mass spectrography, may be used for the collection and analysis of the samples. The information obtained will be used to estimate the total release of volatile organic compounds from TRUSAF to determine the need for air emmission permits.

  4. Hanford facility dangerous waste permit application, PUREX storage tunnels

    Energy Technology Data Exchange (ETDEWEB)

    Price, S.M.

    1997-09-08

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997.

  5. Methods for expanding the capacity of spent fuel storage facilities

    International Nuclear Information System (INIS)

    At the beginning of 1989 more than 55,000 metric tonnes of heavy metal (MTHM) of spent Light Water Reactor (LWR) and Heavy Water Reactor (HWR) fuel had been discharged worldwide from nuclear power plants. Only a small fraction of this fuel has been reprocessed. The majority of the spent fuel assemblies are currently held at-reactor (AR) or away-from-reactor (AFR) in storage awaiting either chemical processing or final disposal depending on the fuel concept chosen by individual countries. Studies made by NEA and IAEA have projected that annual spent fuel arising will reach about 10,000 t HM in the year 2000 and cumulative arising will be more than 200,000 t HM. Taking into account the large quantity of spent fuel discharged from NPP and that the first demonstrations of the direct disposal of spent fuel or HLW are expected only after the year 2020, long-term storage will be the primary option for management of spent fuel until well into the next century. There are several options to expand storage capacity: (1) to construct new away-from-reactor storage facilities, (2) to transport spent fuel from a full at-reactor pool to another site for storage in a pool that has sufficient space to accommodate it, (3) to expand the capacity of existing AR pools by using compact racks, double-tierce, rod consolidation and by increasing the dimensions of existing pools. The purpose of the meeting was: to exchange new information on the international level on the subject connected with the expansion of storage capacities for spent fuel; to elaborate the state-of-the-art of this problem; to define the most important areas for future activity; on the basis of the above information to give recommendations to potential users for selection and application of the most suitable methods for expanding spent fuel facilities taking into account the relevant country's conditions. Refs, figs and tabs

  6. Hanford facility dangerous waste permit application, PUREX storage tunnels

    International Nuclear Information System (INIS)

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997

  7. Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan

    International Nuclear Information System (INIS)

    This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  8. Regulators experiences in licensing and inspection of dry cask storage facilities

    International Nuclear Information System (INIS)

    Full text: All operating nuclear power reactors in the United States (US) are storing spent fuel in NRC licensed on-site spent fuel pools (SFPs). Most reactors were not designed to store, in these pools, the full amount of spent fuel generated during the life of plant operation. Utilities originally planned for spent fuel to remain in the SFPs for a few years after discharge from the reactor core and then to be sent to a reprocessing facility. However, the US Government declared a moratorium on reprocessing in 1977. Although the ban was later lifted, reprocessing has not been pursued as a feasible option. Consequently, utilities expanded the storage capacity of SFPs by the use of high-density storage racks. Eventually, utilities needed additional storage capacity. In response to these needs, NRC provided a regulatory alternative for interim spent fuel storage in dry cask storage systems. For spent fuel management, both pool storage and dry storage are safe methods, but there are significant differences. Pool storage requires a greater operational vigilance on the part of the nuclear power plant to maintain the performance of electrical and mechanical systems using pumps, piping and instrumentation. Dry storage technology uses passive cooling systems with robust cask designs requiring minimal operational vigilance. The United States Nuclear Regulatory Commission (NRC), through the combination of a rigorous licensing and inspection program, ensures the safety and security of dry cask storage. NRC authorizes the storage of spent fuel at an independent spent fuel storage installation (ISFSI) under two licensing options: site-specific licensing and general licensing. In July 1986, the NRC issued the first site-specific license to the Surry Nuclear Power Plant in Virginia, authorizing the interim storage of spent fuel in a dry storage cask configuration. Today, there are over 30 ISFSIs currently licensed by the NRC with over 700 loaded dry casks. Current projections

  9. The CASCAD system: An SGN spent fuel dry storage facility

    International Nuclear Information System (INIS)

    This paper will present SGN's dry vault spent storage system. This concept is based on the CASCAD facility, designed and built by SGN for the French Atomic Energy Commission (CEA) at Cadarache, France. Cascade has been in operation since 1990 since which time SGN has customized its storage system. Because of its extensive experience in both spent fuel assembly and dry storage of high level waste, SGN is able to design solutions fully customized to fit customers' storage requirements using proven technology. Its modular approach allows for staggered investment over a period of several years for maximum flexibility. The Cascad system meets site-specific constraints and safety requirements and is able to receive a wide range of fuels and shipping casks. Since spent fuel assemblies are stored in passive cooled pits, the system is entirely passive and therefore inherently safe. Moreover, the Cascad system allows total retrievability of spent fuel after a 50-year storage period even if the reactor building no longer exists

  10. Study for the selection of a supplementary spent fuel storage facility for KANUPP

    International Nuclear Information System (INIS)

    Steps taken for construction of the spent fuel facility of Karachi Nuclear Power Plant (KANUPP) are the following: choice of conceptual design and site selection; preliminary design and preparation of Preliminary Safety Analysis Report (PSAR); Construction of the facility and preparation of PSAR; testing/commissioning and loading of the storage facility. Characterisation of the spent fuel is essential for design of the storage facility. After comparison of various storage types, it seems that construction of dry storage facility based on concrete canisters at KANUPP site is a suitable option to enhance the storage capacity

  11. Preliminary safety evaluation (PSE) for Sodium Storage Facility at the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    This evaluation was performed for the Sodium Storage Facility (SSF) which will be constructed at the Fast Flux Test Facility (FFTF) in the area adjacent to the South and West Dump Heat Exchanger (DHX) pits. The purpose of the facility is to allow unloading the sodium from the FFTF plant tanks and piping. The significant conclusion of this Preliminary Safety Evaluation (PSE) is that the only Safety Class 2 components are the four sodium storage tanks and their foundations. The building, because of its imminent risk to the tanks under an earthquake or high winds, will be Safety Class 3/2, which means the building has a Safety Class 3 function with the Safety Class 2 loads of seismic and wind factored into the design

  12. Conversion of the EBWR into a radioactive waste storage facility

    International Nuclear Information System (INIS)

    This paper describes the environmental and engineering issues of interest during the conversion of the experimental boiling water reactor (EBWR) into the radioactive waste storage facility (RWSF) at Argonne National Laboratory-East (ANL-E), Argonne, Illinois. The existing EBWR at ANL-E was constructed in the late 1950s. The decontamination and decommissioning of the EBWR is in progress and nearing completion. This facility will be used to provide sufficient radioactive waste storage to meet ANL-E's needs until the Waste Isolation Pilot Plant near Carlsbad, New Mexico, will accept the waste. During the conceptual design phase of the project, the cost for the construction of a new RWSF was estimated at approximately $6.25 million as compared to a $2.7 million estimate for the conversion of the EBWR into the RWSF. These estimates include costs for engineering, permits, and construction. In anticipation of budget recision, ANL took a proactive role to further reduce the project cost by approximately $0.5 million using a value engineering process and redefining the storage requirements

  13. Microbial Condition of Water Samples from Foreign Fuel Storage Facilities

    International Nuclear Information System (INIS)

    In order to assess the microbial condition of foreign spent nuclear fuel storage facilities and their possible impact on SRS storage basins, twenty-three water samples were analyzed from 12 different countries. Fifteen of the water samples were analyzed and described in an earlier report (WSRC-TR-97-00365 [1]). This report describes nine additional samples received from October 1997 through March 1998. The samples include three from Australia, two from Denmark and Germany and one sample from Italy and Greece. Each water sample was analyzed for microbial content and activity as determined by total bacteria, viable aerobic bacteria, viable anaerobic bacteria, viable sulfate-reducing bacteria, viable acid-producing bacteria and enzyme diversity. The results for each water sample were then compared to all other foreign samples analyzed to date and monthly samples pulled from the receiving basin for off-site fuel (RBOF), at SRS. Of the nine samples analyzed, four samples from Italy, Germany and Greece had considerably higher microbiological activity than that historically found in the RBOF. This microbial activity included high levels of enzyme diversity and the presence of viable organisms that have been associated with microbial influenced corrosion in other environments. The three samples from Australia had microbial activities similar to that in the RBOF while the two samples from Denmark had lower levels of microbial activity. These results suggest that a significant number of the foreign storage facilities have water quality standards that allow microbial proliferation and survival

  14. Radon exposure at a radioactive waste storage facility

    International Nuclear Information System (INIS)

    The Waste Management Department of Nuclear and Energy Research Institute (IPEN) is responsible for the safety management of the waste generated at all internal research centers and that of other waste producers such as industry, medical facilities, and universities in Brazil. These waste materials, after treatment, are placed in an interim storage facility. Among them are 226Ra needles used in radiotherapy, siliceous cake arising from conversion processes, and several other classes of waste from the nuclear fuel cycle, which contain Ra-226 producing 222Rn gas daughter. In order to estimate the effective dose for workers due to radon inhalation, the radon concentration at the storage facility has been assessed within this study. Radon measurements have been carried out through the passive method with solid-state nuclear track detectors (CR-39) over a period of nine months, changing detectors every month in order to determine the long-term average levels of indoor radon concentrations. The radon concentration results, covering the period from June 2012 to March 2013, varied from 0.55 ± 0.05 to 5.19 ± 0.45 kBq m−3. The effective dose due to 222Rn inhalation was further assessed following ICRP Publication 65. (paper)

  15. The dynamic storage and restart facilities in MABEL-2

    International Nuclear Information System (INIS)

    MABEL-2 is a FORTRAN program for calculating clad ballooning in a PWR during a LOCA. Originally written with fixed array storage, the use of the code has been extended by including dynamic storage. The lengths of the arrays in the program are set at execution time, varying from run to run. This allows much greater freedom in the choice of mesh and the size of case run. The use of computer memory is also more efficient. In addition a restart facility has been included which allows the user to break off and restart execution of the program (once or many times) during a transient. By using this facility much longer calculations can be run. Should an error in either input data or program become apparent late in a transient, the case need only be re-run from the last dump because some input data can be altered at restart. The use of these new facilities and the coding changes are described. (author)

  16. A New Storage Facility for Institutional Radioactive Wastes at IPEN.

    Science.gov (United States)

    Vicente, Roberto; Dellamano, José Claudio; Potiens, Ademar José

    2015-08-01

    IPEN, the Nuclear and Energy Research Institute in Sao Paulo, Brazil, has been managing the radioactive wastes generated in its own activities of research and radioisotope production as well as those received from many radioisotope users in the country since its start up in 1958. Final disposal options are presently unavailable for the wastes that cannot be managed by release after decay. Treated and untreated wastes including disused sealed radioactive sources and solid and liquid wastes containing radionuclides of the uranium and thorium series or fission and activation products are among the categories that are under safe and secure storage. This paper discusses the aspects considered in the design and describes the startup of a new storage facility for these wastes. PMID:26102323

  17. Reorganizing Nigeria's Vaccine Supply Chain Reduces Need For Additional Storage Facilities, But More Storage Is Required.

    Science.gov (United States)

    Shittu, Ekundayo; Harnly, Melissa; Whitaker, Shanta; Miller, Roger

    2016-02-01

    One of the major problems facing Nigeria's vaccine supply chain is the lack of adequate vaccine storage facilities. Despite the introduction of solar-powered refrigerators and the use of new tools to monitor supply levels, this problem persists. Using data on vaccine supply for 2011-14 from Nigeria's National Primary Health Care Development Agency, we created a simulation model to explore the effects of variance in supply and demand on storage capacity requirements. We focused on the segment of the supply chain that moves vaccines inside Nigeria. Our findings suggest that 55 percent more vaccine storage capacity is needed than is currently available. We found that reorganizing the supply chain as proposed by the National Primary Health Care Development Agency could reduce that need to 30 percent more storage. Storage requirements varied by region of the country and vaccine type. The Nigerian government may want to consider the differences in storage requirements by region and vaccine type in its proposed reorganization efforts. PMID:26858383

  18. Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities

    International Nuclear Information System (INIS)

    In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

  19. Viability of Existing INL Facilities for Dry Storage Cask Handling

    Energy Technology Data Exchange (ETDEWEB)

    Randy Bohachek; Charles Park; Bruce Wallace; Phil Winston; Steve Marschman

    2013-04-01

    This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

  20. Viability of Existing INL Facilities for Dry Storage Cask Handling

    Energy Technology Data Exchange (ETDEWEB)

    Bohachek, Randy; Wallace, Bruce; Winston, Phil; Marschman, Steve

    2013-04-30

    This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

  1. Field Survey of Cactus Crater Storage Facility (Runit Dome)

    Energy Technology Data Exchange (ETDEWEB)

    Douglas Miller, Terence Holland

    2008-10-31

    The US Department of Energy, Office of Health and Safety (DOE/HS-10), requested that National Security Technologies, LLC, Environmental Management directorate (NSTec/EM) perform a field survey of the Cactus Crater Storage Facility (Runit Dome), similar to past surveys conducted at their request. This field survey was conducted in conjunction with a Lawrence Livermore National Laboratory (LLNL) mission on Runit Island in the Enewetak Atoll in the Republic of the Marshall Islands (RMI). The survey was strictly a visual survey, backed up by digital photos and a written description of the current condition.

  2. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    In April 1985, the Department of Energy (DOE) selected the Clinch River site as its preferred site for the construction and operation of the monitored retrievable storage (MRS) facility (USDOE, 1985). In support of the DOE MRS conceptual design activity, available data describing the site have been gathered and analyzed. A composite geotechnical description of the Clinch River site has been developed and is presented herein. This report presents Clinch River site description data in the following sections: general site description, surface hydrologic characteristics, groundwater characteristics, geologic characteristics, vibratory ground motion, surface faulting, stability of subsurface materials, slope stability, and references. 48 refs., 35 figs., 6 tabs

  3. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-12-01

    Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references.

  4. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    Since 1987, Westinghouse Hanford Company has been a major contractor to the U.S. Department of Energy-Richland Operations Office and has served as co-operator of the 3718-F Alkali Metal Treatment and Storage Facility, the waste management unit addressed in this closure plan. The closure plan consists of a Part A Dangerous waste Permit Application and a RCRA Closure Plan. An explanation of the Part A Revision (Revision 1) submitted with this document is provided at the beginning of the Part A section. The closure plan consists of 9 chapters and 5 appendices. The chapters cover: introduction; facility description; process information; waste characteristics; groundwater; closure strategy and performance standards; closure activities; postclosure; and references

  5. Consolidated Storage Facilities: Camel's Nose or Shared Burden? - 13112

    International Nuclear Information System (INIS)

    The Blue Ribbon Commission (BRC) made a strong argument why the reformulated nuclear waste program should make prompt efforts to develop one or more consolidated storage facilities (CSFs), and recommended the amendment of NWPA Section 145(b) 2 (linking 'monitored retrievable storage' to repository development) as an essential means to that end. However, other than recommending that the siting of CSFs should be 'consent-based' and that spent nuclear fuel (SNF) at stranded sites should be first-in-line for removal, the Commission made few recommendations regarding how CSF development should proceed. Working with three other key Senators, Jeff Bingaman attempted in the 112. Congress to craft legislation (S. 3469) to put the BRC recommendations into legislative language. The key reason why the Nuclear Waste Administration Act of 2012 did not proceed was the inability of the four senators to agree on whether and how to amend NWPA Section 145(b). A brief review of efforts to site consolidated storage since the Nuclear Waste Policy Amendments Act of 1987 suggests a strong and consistent motivation to shift the burden to someone (anyone) else. This paper argues that modification of NWPA Section 145(b) should be accompanied by guidelines for regional development and operation of CSFs. After review of the BRC recommendations regarding CSFs, and the 'camel's nose' prospects if implementation is not accompanied by further guidelines, the paper outlines a proposal for implementation of CSFs on a regional basis, including priorities for removal from reactor sites and subsequently from CSFs to repositories. Rather than allowing repository siting to be prejudiced by the location of a single remote CSF, the regional approach limits transport for off-site acceptance and storage, increases the efficiency of removal operations, provides a useful basis for compensation to states and communities that accept CSFs, and gives states with shared circumstances a shared stake in storage and

  6. Simulation of mass storage systems operating in a large data processing facility

    Science.gov (United States)

    Holmes, R.

    1972-01-01

    A mass storage simulation program was written to aid system designers in the design of a data processing facility. It acts as a tool for measuring the overall effect on the facility of on-line mass storage systems, and it provides the means of measuring and comparing the performance of competing mass storage systems. The performance of the simulation program is demonstrated.

  7. Interface Between the Storage of Spent Fuels at Japan’s Interim Storage Facility and the Transport There of after Storage in Japan. Annex VII

    International Nuclear Information System (INIS)

    The Recyclable-Fuel Storage Company (RFS) plans to construct Japan’s first interim storage facility for spent fuels of light water reactors. This facility is designed to have no equipment to refill spent fuels. It stores transported casks as they are. After storage, casks are carried out from the facility without opening their lids and transported to a reprocessing facility and others. Spent fuels are planned to be stored for 50 years. In other words, as spent fuels are transported after storage in the same state as they are carried into the interim storage facility, it is necessary to consider the transportation 50 years later in designing the cask. Here, we examined the points to be taken into account for storage in consideration of transportation 50 years later

  8. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    This report presents a summary design description of the Conceptual Design for an Integral Monitored Retrievable Storage (MRS) Facility, as prepared by The Ralph M. Parsons Company under an A-E services contract with the Richland Operations Office of the Department of Energy. More detailed design requirements and design data are set forth in the Basis for Design and Design Report, bound under separate cover and available for reference by those desiring such information. The design data provided in this Design Report Executive Summary, the Basis for Design, and the Design Report include contributions by the Waste Technology Services Division of Westinghouse Electric Corporation (WEC), which was responsible for the development of the waste receiving, packaging, and storage systems, and Golder Associates Incorporated (GAI), which supported the design development with program studies. The MRS Facility design requirements, which formed the basis for the design effort, were prepared by Pacific Northwest Laboratory for the US Department of Energy, Richland Operations Office, in the form of a Functional Design Criteria (FDC) document, Rev. 4, August 1985. 9 figs., 6 tabs

  9. Recommendations on the proposed Monitored Retrievable Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    1985-10-01

    Following the Department of Energy`s announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE`s primary and secondary sites, were invited to participate in the state`s review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor`s Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

  10. Recommendations on the proposed Monitored Retrievable Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    1985-10-01

    Following the Department of Energy's announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE's primary and secondary sites, were invited to participate in the state's review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor's Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

  11. Monitored retrievable storage submission to Congress: Volume 2, Environmental assessment for a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    This Environmental Assessment (EA) supports the DOE proposal to Congress to construct and operate a facility for monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portion of Oak Ridge, Tennessee. The first part of this document is an assessment of the value of, need for, and feasibility of an MRS facility as an integral component of the waste management system. The second part is an assessment and comparison of the potential environmental impacts projected for each of six site-design combinations. The MRS facility would be centrally located with respect to existing reactors, and would receive and canister spent fuel in preparation for shipment to and disposal in a geologic repository. 207 refs., 57 figs., 132 tabs

  12. Concept for an ultimate storage facility for heat-generating radioactive waste in clay stone in Germany

    International Nuclear Information System (INIS)

    According to the German reference ultimate storage concept heat-generating radioactive waste from the operation of nuclear power stations should be stored permanently maintenance-free and in a non-recoverable manner in a salt formation. Within the framework of investigations into the utilisation of alternative host rocks a concept for an ultimate storage facility in clay stone was developed in an R and D project. For this purpose all important aspects of the design, development, operation and shutdown were taken into account for a model region in northern Germany. It was established that storage in 50 m deep vertical boreholes in a mine at a depth of about 350 m appears to be the most practical solution for an ultimate storage facility in clay stone. Compared to the reference concept in salt an ultimate storage facility in clay stone requires solid support of all mine openings with steel arches or shotcrete. Because of the lower maximum permissible temperature in the backfilling material (bentonite) the area required for the ultimate storage facility is about five times larger. A period of more than 100 years is estimated from survey to shutdown. (orig.)

  13. Conceptual Design of an Antiproton Generation and Storage Facility

    International Nuclear Information System (INIS)

    The Antiproton Generation and Storage Facility (AGSF) creates copious quantities of antiprotons, for bottling and transportation to remote cancer therapy centers. The first step in the generation and storage process is to accelerate an intense proton beam down the Main Linac for injection into the Main Ring, which is a Rapid Cycling Synchrotron that accelerates the protons to high energy. The beam is then extracted from the ring into a transfer line and into a Proton Target. Immediately downstream of the target is an Antiproton Collector that captures some of the antiprotons and focuses them into a beam that is transported sequentially into two antiproton rings. The Precooler ring rapidly manipulates antiproton bunches from short and broad (in momentum) to long and thin. It then performs some preliminary beam cooling, in the fraction of a second before the next proton bunch is extracted from the Main Ring. Pre-cooled antiprotons are passed on to the Accumulator ring before the next antiprotons arrive from the target. The Accumulator ring cools the antiprotons, compressing them into a dense state that is convenient for mass storage over many hours. Occasionally the Accumulator ring decelerates a large number of antiprotons, injecting them into a Deceleration Linac that passes them into a waiting Penning trap

  14. Conceptual Design of an Antiproton Generation and Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Peggs, Stephen

    2006-10-24

    The Antiproton Generation and Storage Facility (AGSF) creates copious quantities of antiprotons, for bottling and transportation to remote cancer therapy centers. The first step in the generation and storage process is to accelerate an intense proton beam down the Main Linac for injection into the Main Ring, which is a Rapid Cycling Synchrotron that accelerates the protons to high energy. The beam is then extracted from the ring into a transfer line and into a Proton Target. Immediately downstream of the target is an Antiproton Collector that captures some of the antiprotons and focuses them into a beam that is transported sequentially into two antiproton rings. The Precooler ring rapidly manipulates antiproton bunches from short and broad (in momentum) to long and thin. It then performs some preliminary beam cooling, in the fraction of a second before the next proton bunch is extracted from the Main Ring. Pre-cooled antiprotons are passed on to the Accumulator ring before the next antiprotons arrive from the target. The Accumulator ring cools the antiprotons, compressing them into a dense state that is convenient for mass storage over many hours. Occasionally the Accumulator ring decelerates a large number of antiprotons, injecting them into a Deceleration Linac that passes them into a waiting Penning trap.

  15. 36 CFR 1234.14 - What are the requirements for environmental controls for records storage facilities?

    Science.gov (United States)

    2010-07-01

    ... environmental controls for records storage facilities? 1234.14 Section 1234.14 Parks, Forests, and Public... STORAGE FACILITIES Facility Standards § 1234.14 What are the requirements for environmental controls for..., see § 1234.3); (2) ANSI/NAPM IT9.23 (incorporated by reference, see § 1234.3); (3) ANSI/PIMA...

  16. Hazards assessment for the Hazardous Waste Storage Facility

    International Nuclear Information System (INIS)

    This report documents the hazards assessment for the Hazardous Waste Storage Facility (HWSF) located at the Idaho National Engineering Laboratory. The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. The hazards assessment identifies and analyzes hazards that are significant enough to warrant consideration in a facility's operational emergency management program. The area surrounding HWSF, the buildings and structures at HWSF, and the processes used at HWSF are described in this report. All nonradiological hazardous materials at the HWSF were identified (radiological hazardous materials are not stored at HWSF) and screened against threshold quantities according to DOE Order 5500.3A guidance. Two of the identified hazardous materials exceeded their specified threshold quantity. This report discusses the potential release scenarios and consequences associated with an accidental release for each of the two identified hazardous materials, lead and mercury. Emergency considerations, such as emergency planning zones, emergency classes, protective actions, and emergency action levels, are also discussed based on the analysis of potential consequences. Evaluation of the potential consequences indicated that the highest emergency class for operational emergencies at the HWSF would be a Site Area Emergency

  17. Establishing a central waste processing and storage facility in Ghana

    International Nuclear Information System (INIS)

    Radioactive waste and spent sealed sources in Ghana are generated from various nuclear applications - diagnostic and therapeutic procedures in medicine, measurement and processing techniques in industry, irradiation techniques for food preservation and sterilization of medical products and a research reactor for research and teaching. Statistics available indicate that over 15 institutions in Ghana are authorized to handle radiation sources. At present radioactive waste and spent sealed sources are collected and stored in the interim facility without conditioning. With the increasing use of radioactive sources in the industry, medicine for diagnostic and therapeutic purpose and research and teaching, the volume of waste is expected to increase. The radioactive waste expected include spent ion exchange resins from the nuclear reactor water purification system, incompactible solid waste from mechanical filter, liquid and organic waste and spent sealed sources. It is estimated that four 200L drums will be needed annually to condition the waste to be generated. The National Radioactive Waste Management Centre (NRWMC) was therefore established to carry radioactive waste safety operations in Ghana and research to ensure that each waste type is managed in the most appropriate manner. Its main task includes development and establishment of the radioactive waste management infrastructure with a capacity considering the future nuclear technology development in Ghana. The first phase covers the establishment of administrative structure, development of basic regulations and construction of the radioactive waste processing and storage facility. The Ghana Radioactive Waste Management regulation has been presented to the Parliament of Ghana for consideration. The initial draft was reviewed by the RPB. A 3-day national seminar on the Understanding and Implementation of the Regulation on Radioactive Waste Management in Ghana was held to discuss and educate the general public on the

  18. Interface Issues Arising in Interim Storage Facilities Using Storage/Transport Dual Purpose Dry Metal Casks in Japan. Annex VIII

    International Nuclear Information System (INIS)

    The annual amount of spent fuels (SFs) discharged by the operation of commercial reactors nowadays is estimated to be around 10 000 tU level worldwide. While the amount of SFs already reprocessed account about one-third, the rest are currently stored in storage facilities, typically, in wet pools attached to nuclear power plants (NPPs). Cumulative amount of SFs stored is estimated to be about 250 000 tU by 2010 (I. Hanaki, Japan). While wet pool system is dominant in storage facility designs, new design concepts for storage facilities have been continuously developed. One of these new designs is that using dual purpose dry metal casks. “Dual” here means that the casks are not only designed as storage containers, but also designed as transport containers that will satisfy relevant regulatory requirements for transport of radioactive materials such as TS-R-1. Advantage of adopting such “dual” design in storage facilities lies in that this could contribute to reduce the burden associated with handling operations, because, under such designs, SFs once loaded into casks can easily be “transported” to storage facilities, and after storage of several decades, they can again be “transported” to their destinations, regardless they are reprocessing facilities or final disposal sites. Other than these, adopting this kind of design can reduce the amount of radioactive wastes discharged through storage operation, thus can reduce operation costs while maintaining safety level. In Japan, where 53 commercial NPPs are now in operation and with the annual amount of SFs produced sums up to about 1000 tU, keen needs are perceived among SFs producers (namely, utilities) to secure adequate SFs storage capacity. Therefore, a new application for constructing storage facility of 3000 tU scale in Mutsu city, located in northern part of Aomori prefecture, has been submitted in March 2007 by a subsidiary company of utilities named RFS (Recyclable Fuel Storage Company), using

  19. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    International Nuclear Information System (INIS)

    The Solid Waste Treatment Facility, referred to throughout this document as T Plant, has been identified as the location where sludge from the K Basin fuel storage facilities will be stored until final disposition of the material occurs

  20. Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

    International Nuclear Information System (INIS)

    700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage

  1. Retrievable surface storage facility conceptual system design description

    International Nuclear Information System (INIS)

    The studies evaluated several potentially attractive methods for processing and retrievably storing high-level radioactive waste after delivery to the Federal repository. These studies indicated that several systems could be engineered to safely store the waste, but that the simplest and most attractive concept from a technical standpoint would be to store the waste in a sealed stainless steel canister enclosed in a 2 in. thick carbon steel cask which in turn would be inserted into a reinforced concrete gamma-neutron shield, which would also provide the necessary air-cooling through an air annulus between the cask and the shield. This concept best satisfies the requirements for safety, long-term exposure to natural phenomena, low capital and operating costs, retrievability, amenability to incremental development, and acceptably small environmental impact. This document assumes that the reference site would be on ERDA's Hanford reservation. This document is a Conceptual System Design Description of the facilities which could satisfy all of the functional requirements within the established basic design criteria. The Retrievable Surface Storage Facility (RSSF) is planned with the capacity to process and store the waste received in either a calcine or glass/ceramic form. The RSSF planning is based on a modular development program in which the modular increments are constructed at rates matching projected waste receipts

  2. 190-C Facility <90 Day Storage Pad supplemental information to the Hanford facility contingency plan

    International Nuclear Information System (INIS)

    The 190-C Facility <90 Day Storage Pad stores waste oils primarily contaminated with lead generated while draining equipment within the building of residual lubricating oils. Waste oils are packaged and stored in fifty-five gallon drums, or other containers permitted by the Site Specific Waste Management Instruction. Bechtel Hanford, Inc. (BHI) manual BHI-EE-02, Environmental Requirements Procedures, references this document. This document is to be used to demonstrate compliance with the contingency plan requirements in Washington Administrative Code, Chapter 173-303, Dangerous Waste Regulations, for certain Resource Conservation and Recovery Act of 1976 (RCRA) waste management units (units). Refer to BHI-EE-02, for additional information

  3. Alternate airborne release fraction determination for hazardous waste management storage repository hazard categorization at the Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Hazardous Waste Management (HWM) facilities are used in the handling and processing of solid and liquid radioactive, hazardous, mixed, and medical wastes generated at Lawrence Livermore National Laboratory (LLNL). Waste may be treated or stored in one of the HWM facility units prior to shipment off site for treatment or disposal. Planned facilities such as the Decontamination and Waste Treatment Facility (DWTF) and the Building 280 Container Storage Unit are expected to handle similar waste streams. A hazard classification was preformed in each facility safety analysis report (SAR) according to the DOE Standard 1027-92 'Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports.' The general methodology practiced by HWM to determine alternate airborne release fractions (ARFs) in those SARs was based upon a beyond evaluation basis earthquake accident scenario characterized by the release of the largest amount of respirable, airborne radioactive material. The alternate ARF was calculated using a three-factor formula consisting of the fraction of failed waste containers, fraction of material released from failed waste containers,and the fraction of material entrained to the environment. Recently, in deliberation with DOE-Oakland representatives, HWM decided to modify this methodology. In place of the current detailed analysis, a more straightforward process was proposed based upon material form, credible accident environments, and empirical data. This paper will discuss the methodology and derivation of ARFs specific to HWM treatment and storage facilities that are alternative to those presented in DOE-STD-1027-92

  4. Block dry storage facility for the intermediate storage of spent fuel elements and vitrified high-level waste

    International Nuclear Information System (INIS)

    The article describes a vault-type store for dry storage of spent fuel from nuclear power plants or vitrified high-level waste from reprocessing plants. Heat is removed from the storage facility by natural air convection with a passive direct or indirect cooling circuit. (orig.)

  5. REVIEW OF FAST FLUX TEST FACILITY (FFTF) FUEL EXPERIMENTS FOR STORAGE IN INTERIM STORAGE CASKS (ISC)

    Energy Technology Data Exchange (ETDEWEB)

    CHASTAIN, S.A.

    2005-10-24

    Appendix H, Section H.3.3.10.11 of the Final Safety Analysis Report (FSAR), provides the limits to be observed for fueled components authorized for storage in the Fast Flux Test Facility (FFTF) spent fuel storage system. Currently, the authorization basis allows standard driver fuel assemblies (DFA), as described in the FSAR Chapter 17, Section 17.5.3.1, to be stored provided decay power per assembly is {le} 250 watts, post-irradiation time is four years minimum, average assembly burn-up is 150,000 MWD/MTHM maximum and the pre-irradiation enrichment is 29.3% maximum (per H.3.3.10.11). In addition, driver evaluation (DE), core characterizer assemblies (CCA), and run-to-cladding-breach (RTCB) assemblies are included based on their similarities to a standard DFA. Ident-69 pin containers with fuel pins from these DFAs can also be stored. Section H.3.3.10.11 states that fuel types outside the specification criteria above will be addressed on a case-by-case basis. There are many different types of fuel and blanket experiments that were irradiated in the FFTF which now require offload to the spent fuel storage system. Two reviews were completed for a portion of these special type fuel components to determine if placement into the Core Component Container (CCC)/Interim Storage Cask (ISC) would require any special considerations or changes to the authorization basis. Project mission priorities coupled with availability of resources and analysts prevented these evaluations from being completed as a single effort. Areas of review have included radiological accident release consequences, radiological shielding adequacy, criticality safety, thermal limits, confinement, and stress. The results of these reviews are available in WHC-SD-FF-RPT-005, Rev. 0 and 1, ''Review of FFTF Fuel Experiments for Storage at ISA'', (Reference I), which subsequently allowed a large portion of these components to be included in the authorization basis (Table H.3.3-21). The

  6. REVIEW OF FAST FLUX TEST FACILITY (FFTF) FUEL EXPERIMENTS FOR STORAGE IN INTERIM STORAGE CASKS (ISCs)

    International Nuclear Information System (INIS)

    Appendix H, Section H.3.3.10.11 of the Final Safety Analysis Report (FSAR), provides the limits to be observed for fueled components authorized for storage in the Fast Flux Test Facility (FFTF) spent fuel storage system. Currently, the authorization basis allows standard driver fuel assemblies (DFA), as described in the FSAR Chapter 17, Section 17.5.3.1, to be stored provided decay power per assembly is (le) 250 watts, post-irradiation time is four years minimum, average assembly burn-up is 150,000 MWD/MTHM maximum and the pre-irradiation enrichment is 29.3% maximum (per H.3.3.10.11). In addition, driver evaluation (DE), core characterizer assemblies (CCA), and run-to-cladding-breach (RTCB) assemblies are included based on their similarities to a standard DFA. Ident-69 pin containers with fuel pins from these DFAs can also be stored. Section H.3.3.10.11 states that fuel types outside the specification criteria above will be addressed on a case-by-case basis. There are many different types of fuel and blanket experiments that were irradiated in the FFTF which now require offload to the spent fuel storage system. Two reviews were completed for a portion of these special type fuel components to determine if placement into the Core Component Container (CCC)/Interim Storage Cask (ISC) would require any special considerations or changes to the authorization basis. Project mission priorities coupled with availability of resources and analysts prevented these evaluations from being completed as a single effort. Areas of review have included radiological accident release consequences, radiological shielding adequacy, criticality safety, thermal limits, confinement, and stress. The results of these reviews are available in WHC-SD-FF-RPT-005, Rev. 0 and 1, ''Review of FFTF Fuel Experiments for Storage at ISA'', (Reference I), which subsequently allowed a large portion of these components to be included in the authorization basis (Table H.3.3-21). The report also identified

  7. Groundwater Impact Assessment of Tailings Storage Facility, Western Turkey

    Science.gov (United States)

    Peksezer-Sayit, A.; Yazicigil, H.

    2015-12-01

    A tailings storage facility (TSF) is a fundamental part of the mining process and should be carefully designed and managed to prevent any adverse environmental effects. TSF is site-specific and its design criteria are determined by regulations. The new mine waste regulation for the deposition of hazardous waste in a tailings storage facility in Turkey enforces, from bottom to top, 0.5 m thick compacted clay layer with K less than or equal to 1X10-9 m/s , 2 mm thick HDPE geomembrane, and a protective natural material or geotextile. Although these criteria seem to be enough to prevent leakage from the base, in practice, manufacturing and application errors may cause leakage and subsequent contamination of groundwater. The purpose of this study is to assess potential impacts of leakage from the base of TSF on groundwater quality both in operational and post-closure period of a mine site in western Turkey. For this purpose, analytical and 2-D and 3-D numerical models are used together. The potential leakage rate of sulphate-bearing solution from the base of TSF is determined from analytical model. 2-D finite element models (SEEP/W and CTRAN/W) are used to simulate unsaturated flow conditions and advective-dispersive contaminant transport below the TSF under steady-state and transient conditions for the operating period. The long-term impacts of leakage from the base of TSF on groundwater resources are evaluated by 3-D numerical groundwater flow (MODFLOW) and contaminant transport models (MT3DMS). The model results suggest that sulphate-bearing solution leaking from the base of TSF can reach water table in about 290 years. Hence, during the operational period (i.e. 21 years), no interaction is expected between the solution and groundwater. Moreover, long-term simulation results show that about 500 years later, the sulphate concentration in groundwater will be below the maximum allowable limits (i.e. 250 mg/L).

  8. Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes

    International Nuclear Information System (INIS)

    The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables

  9. Heat removal tests on dry storage facilities for nuclear spent fuels

    International Nuclear Information System (INIS)

    In Japan, spent fuel generated in NPP is controlled and stored in dry storage facility away-from reactor. Natural convection cooling system of the storage facility is considered advantageous from both safety and economic point of view. In order to realize this type of facility it is necessary to develop an evaluation method for natural convection characteristics and to make a rational design taking account safety and economic factors. Heat removal tests with the reduces scale models of storage facilities (cask, vault and silo) identified the the flow pattern in the test modules. The temperature and velocity distributions were obtained and the heat transfer characteristics were evaluated

  10. Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction

  11. Fuel Assemblies Thermal Analysis in the New Spent Fuel Storage Facility at Inshass Site

    International Nuclear Information System (INIS)

    New Wet Storage Facility (NSF) is constructed at Inshass site to solve the problem of spent fuel storage capacity of ETRR-1 reactor . The Engineering Safety Heat Transfer Features t hat characterize the new facility are presented. Thermal analysis including different scenarios of pool heat load and safety limits are discussed . Cladding temperature limit during handling and storage process are specified for safe transfer of fuel

  12. Evaluation of heat removal system by natural convection in spent fuel dry storage facilities

    International Nuclear Information System (INIS)

    To use dry storage technology in a large capacity storage facility, it is necessary to have an optimum heat removal design. To optimize such a design, it is important to evaluate the natural cooling efficiency and the limit of the cooling system by natural convection, and to establish the analytical method. For the purposes of this study, the evaluation method of a heat removal system at the cask, vault and silo storage facility is developed. 3 figs

  13. Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    King, J.W.

    1993-08-01

    The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

  14. MRS systems study, Task F: Transportation impacts of a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    The passage of the Nuclear Waste Policy Amendments Act of 1987 (NWPAA) modified the basis from which the Office of Civilian Radioactive Waste Management (OCRWM) had derived and developed the configuration of major elements of the waste system (repository, monitored retrievable storage, and transportation). While the key aspects of the Nuclear Waste Policy Act of 1982 remain unaltered, NWPAA provisions focusing site characterization solely at Yucca Mountain, authorizing a monitored retrievable storage (MRS) facility with specific linkages to the repository, and establishing an MRS Review Commission make it prudent for OCRWM to update its analysis of the role of the MRS in the overall waste system configuration. This report documents the differences in transportation costs and radiological dose under alternative scenarios pertaining to a nuclear waste management system with and without an MRS, to include the effect of various MRS packaging functions and locations. The analysis is limited to the impacts of activities related directly to the hauling of high-level radioactive waste (HLW), including the capital purchase and maintenance costs of the transportation cask system. Loading and unloading impacts are not included in this study because they are treated as facility costs in the other task reports. Transportation costs are based on shipments of 63,000 metric tons of uranium (MTU) of spent nuclear fuel and 7,000 MTU equivalent of HLW. 10 refs., 41 tabs

  15. Quantitative risk analysis of oil storage facilities in seismic areas.

    Science.gov (United States)

    Fabbrocino, Giovanni; Iervolino, Iunio; Orlando, Francesca; Salzano, Ernesto

    2005-08-31

    Quantitative risk analysis (QRA) of industrial facilities has to take into account multiple hazards threatening critical equipment. Nevertheless, engineering procedures able to evaluate quantitatively the effect of seismic action are not well established. Indeed, relevant industrial accidents may be triggered by loss of containment following ground shaking or other relevant natural hazards, either directly or through cascade effects ('domino effects'). The issue of integrating structural seismic risk into quantitative probabilistic seismic risk analysis (QpsRA) is addressed in this paper by a representative study case regarding an oil storage plant with a number of atmospheric steel tanks containing flammable substances. Empirical seismic fragility curves and probit functions, properly defined both for building-like and non building-like industrial components, have been crossed with outcomes of probabilistic seismic hazard analysis (PSHA) for a test site located in south Italy. Once the seismic failure probabilities have been quantified, consequence analysis has been performed for those events which may be triggered by the loss of containment following seismic action. Results are combined by means of a specific developed code in terms of local risk contour plots, i.e. the contour line for the probability of fatal injures at any point (x, y) in the analysed area. Finally, a comparison with QRA obtained by considering only process-related top events is reported for reference. PMID:15908107

  16. Remote monitoring design concepts for spent fuel storage facilities

    International Nuclear Information System (INIS)

    For the past two years Sandia National Laboratories (SNL) has been involved in developing and installing Remote Monitoring Systems (RMS) at a number of sites around the world. Through the cooperation of the various countries and facilities, it has been possible to collect data on the requirements and performance of these systems that are for monitoring the movement of spent nuclear fuel. The data collected shows that the front end detection method can be a very useful concept to reduce the amount of data that has to be collected and, more importantly, reviewed by inspectors. Spent fuel storage monitoring is a major part of the non-proliferation monitoring that must be done since spent fuel is the by-product of all the power and research reactors worldwide. The movement of spent fuel is easier in many respects to monitor since it always requires protective shielding. This paper will describe a number of the Remote Monitoring Systems that have been installed to monitor spent fuel movement and the resulting decrease in data from the use of a sensor-driven front detection system. The reduction of the data collected and stored is also important to remote monitoring since it decreases the time required to transmit the data to a review site

  17. Immobilized high-level waste interim storage alternatives generation and analysis and decision report

    International Nuclear Information System (INIS)

    This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward

  18. Immobilized high-level waste interim storage alternatives generation and analysis and decision report

    Energy Technology Data Exchange (ETDEWEB)

    CALMUS, R.B.

    1999-05-18

    This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward.

  19. Indian Experience In Commissioning, Operation and Safety of Wet Type Spent Fuel Storage Facilities

    International Nuclear Information System (INIS)

    The Indian Nuclear Power Programme is heavily based on PHWR. The spent fuels generated in Indian PHWRs are stored in water pools At Reactor and Fuel storage Facilities for interim periods before reprocessing. The technology of design, construction, commissioning and operation of these fuel storage facilities has been mastered by BARC. Some of the innovative features and operating experience of these facilities are described in this paper. (author)

  20. Development of a novel interim bulk fuel storage facility for the PBMR / W.F. Fuls

    OpenAIRE

    Fuls, Wilhelm Franz

    2004-01-01

    The PBMR is the first High Temperature Reactor being designed for commercial power generation in South Africa. It makes use of spherical fuel elements, containing coated uranium oxide particles encapsulated in a graphite matrix. The spent fuel generated from the reactor is stored in a storage system before final disposal. Such storage systems are called interim storage facilities, and normally make use of small transportable containers. The PBMR design makes use of bulk storage containers...

  1. Evaluation of alternatives for the future of facilities at the Western New York Nuclear Service Center

    International Nuclear Information System (INIS)

    Regulatory considerations are discussed. Alternatives for the continued operation or decommissioning of the state-licensed burial area, the low-level waste treatment facilities, and the NRC licensed burial area are evaluated. Radiological impact analyses were also performed for alternatives on other facilities

  2. 75 FR 53371 - Liquefied Natural Gas Facilities: Obtaining Approval of Alternative Vapor-Gas Dispersion Models

    Science.gov (United States)

    2010-08-31

    ... Pipeline and Hazardous Materials Safety Administration Liquefied Natural Gas Facilities: Obtaining Approval... Safety Administration (PHMSA) issues federal safety standards for siting liquefied natural gas (LNG...) NFPA 59A: Standard for the Production, Storage, and Handling of Liquefied Natural Gas. That...

  3. Alternative Data Storage Solution for Mobile Messaging Services

    Directory of Open Access Journals (Sweden)

    David C. C. Ong

    2007-01-01

    Full Text Available In recent years, mobile devices have become relatively more powerful with additional features which have the capability to provide multimedia streaming. Better, faster and more reliable data storage solutions in the mobile messaging platform have become more essential with these additional improvements. The existing mobile messaging infrastructure, in particular the data storage platform has become less proficient in coping with the increased demand for its services. This demand especially in the mobile messaging area (i.e. SMS – Short Messaging Service, MMS – Multimedia Messaging Service, which may well exceeded 250,000 requests per second, means that the need to evaluate competing data management systems has become not only necessary but essential. This paper presents an evaluation of SMS and MMS platforms using different database management systems – DBMS and recommends the best data management strategies for these platforms.

  4. Study on the Maximization of Durable Years of the Underground Oil Storage Facility

    International Nuclear Information System (INIS)

    Objectives of the study on the maximization of durable years of the underground oil storage facility are as follows - Establishment of the detailed field of study and methodology for the preparation of guideline of operation and maintenance of underground oil storage facility - Preparation of program for the assessment of the impedimental factor of safety such as clogging and seawater intrusion. The study sites are Yeosu, Pyeongtaek, Ulsan underground oil storage facilities which are operated by KNOC, SK gas and E1. Various pending problems of each facilities were summarized and assessed. Long-term program for the maximization of durable years of the underground oil storage facility was prepared based on the results of the assessment of each study sites

  5. HEU to LEU conversion and blending facility: UNH blending alternative to produce LEU oxide for disposal

    International Nuclear Information System (INIS)

    The United States Department of Energy (DOE) is examining options for the disposition of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. Disposition is a process of use or disposal of material that results in the material being converted to a form that is substantially and inherently more proliferation-resistant than is the original form. Examining options for increasing the proliferation resistance of highly enriched uranium (HEU) is part of this effort. This report provides data to be used in the environmental impact analysis for the uranyl nitrate hexahydrate blending option to produce oxide for disposal. This the Conversion and Blending Facility (CBF) alternative will have two missions (1) convert HEU materials into HEU uranyl nitrate (UNH) and (2) blend the HEU uranyl nitrate with depleted and natural assay uranyl nitrate to produce an oxide that can be stored until an acceptable disposal approach is available. The primary emphasis of this blending operation will be to destroy the weapons capability of large, surplus stockpiles of HEU. The blended LEU product can only be made weapons capable again by the uranium enrichment process. The blended LEU will be produced as a waste suitable for storage or disposal

  6. Unsaturated zone investigation at the radioactive waste storage facility site

    Energy Technology Data Exchange (ETDEWEB)

    Skuratovic, Zana; Mazeika, Jonas; Petrosius, Rimantas; Jakimaviciute-Maseliene, Vaidote [Nature Research Centre, Akademijos St. 2, LT-08412, Vilnius (Lithuania); Klizas, Petras; Mokrik, Robert [Vilnius University, M.K. Ciurlionio St. 21/27, LT-03101 Vilnius (Lithuania)

    2014-07-01

    Unsaturated zone is an important part of water circulation cycle and an integral part of many hydrological and hydrogeological factors and processes. The soils of unsaturated zone are regarded as the first natural barrier to a large extent able to limit the spread of contaminants. Nuclear waste disposal site (Maisiagala radioactive waste storage facility site) was analysed in terms of the moisture movement through the unsaturated zone. Extensive data sets of the hydraulic properties, water content and isotope composition have been collected and summarized. The main experimental and observational tasks included the collection of soil samples; determination of the physical properties and the hydraulic conductivity values of soil samples, moisture extraction from the soil sample for isotopic studies; observation of the groundwater dynamics at the Maisiagala piezometer; groundwater sampling for isotopic analysis ({sup 3}H, {sup 18}O/{sup 16}O, {sup 2}H/{sup 1}H ); and monthly precipitation isotopic analysis. Distribution features of globally widespread radionuclide tritium ({sup 3}H) and the water molecule tracer isotopes in precipitation, unsaturated zone soil moisture profiles and groundwater were determined. It was used the well-known unsaturated flow and transport model of HYDRUS-1D (Simunek et al., 2008). In this study, van Genuchten equations for the retention and conductivity estimations have been used. The retention characteristics and van Genuchten model parameters were estimated internally by HYDRUS based on the empirical equations involved in the program. Basic inputs of the tritium transport simulation are the tritium input function and meteorological variables (precipitation and potential evapotranspiration). In order to validate the representativeness of the hydraulic parameters, the model has been used to estimate the tritium distribution in the unsaturated zone, which properly represents the dynamics of the unsaturated zone. The uniformity of the daily

  7. Unsaturated zone investigation at the radioactive waste storage facility site

    International Nuclear Information System (INIS)

    Unsaturated zone is an important part of water circulation cycle and an integral part of many hydrological and hydrogeological factors and processes. The soils of unsaturated zone are regarded as the first natural barrier to a large extent able to limit the spread of contaminants. Nuclear waste disposal site (Maisiagala radioactive waste storage facility site) was analysed in terms of the moisture movement through the unsaturated zone. Extensive data sets of the hydraulic properties, water content and isotope composition have been collected and summarized. The main experimental and observational tasks included the collection of soil samples; determination of the physical properties and the hydraulic conductivity values of soil samples, moisture extraction from the soil sample for isotopic studies; observation of the groundwater dynamics at the Maisiagala piezometer; groundwater sampling for isotopic analysis (3H, 18O/16O, 2H/1H ); and monthly precipitation isotopic analysis. Distribution features of globally widespread radionuclide tritium (3H) and the water molecule tracer isotopes in precipitation, unsaturated zone soil moisture profiles and groundwater were determined. It was used the well-known unsaturated flow and transport model of HYDRUS-1D (Simunek et al., 2008). In this study, van Genuchten equations for the retention and conductivity estimations have been used. The retention characteristics and van Genuchten model parameters were estimated internally by HYDRUS based on the empirical equations involved in the program. Basic inputs of the tritium transport simulation are the tritium input function and meteorological variables (precipitation and potential evapotranspiration). In order to validate the representativeness of the hydraulic parameters, the model has been used to estimate the tritium distribution in the unsaturated zone, which properly represents the dynamics of the unsaturated zone. The uniformity of the daily input in each month should be kept

  8. Commissioning and operation of high level radioactive waste vitrification and storage facilities: the Indian experience

    International Nuclear Information System (INIS)

    In India, R and D work for management of high-level radioactive liquid waste (HLW) was started along with inception of the Indian Atomic Energy Programme. This culminated in the setting up of the first vitrification facility at the Waste Immobilisation Plant (WIP) at Tarapur. The second vitrification facility has been commissioned at WIP at Trombay and the third such facility is being set up at Kalpakkam. Vitrified waste product (VWP) canisters generated from both Tarapur and Trombay are destined for storage at solid storage surveillance facility (SSSF) at Tarapur, which is the first Indian facility for interim storage vitrified waste product. This paper presents the details of commissioning and operation of these facilities along with work being done on long-term characterisation of vitrified waste product and future vitrification programme. (author)

  9. 42 CFR 124.516 - Charitable facility compliance alternative.

    Science.gov (United States)

    2010-10-01

    ... facility may qualify for a provisional certification under this section if it provides an assurance that... certification will be sought, the facility must submit to the Secretary an assurance, together with such... paragraph (f)(1)(i) of this section; or (B) Submit an independent certified audit, conducted in...

  10. Preliminary assessment of radiological doses in alternative waste management systems without an MRS facility

    International Nuclear Information System (INIS)

    This report presents generic analyses of radiological dose impacts of nine hypothetical changes in the operation of a waste management system without a monitored retrievable storage (MRS) facility. The waste management activities examined in this study include those for handling commercial spent fuel at nuclear power reactors and at the surface facilities of a deep geologic repository, and the transportation of spent fuel by rail and truck between the reactors and the repository. In the reference study system, the radiological doses to the public and to the occupational workers are low, about 170 person-rem/1000 metric ton of uranium (MTU) handled with 70% of the fuel transported by rail and 30% by truck. The radiological doses to the public are almost entirely from transportation, whereas the doses to the occupational workers are highest at the reactors and the repository. Operating alternatives examined included using larger transportation casks, marshaling rail cars into multicar dedicated trains, consolidating spent fuel at the reactors, and wet or dry transfer options of spent fuel from dry storage casks. The largest contribution to radiological doses per unit of spent fuel for both the public and occupational workers would result from use of truck transportation casks, which are smaller than rail casks. Thus, reducing the number of shipments by increasing cask sizes and capacities (which also would reduce the number of casks to be handled at the terminals) would reduce the radiological doses in all cases. Consolidating spent fuel at the reactors would reduce the radiological doses to the public but would increase the doses to the occupational workers at the reactors

  11. Hazardous Material Storage Facilities and Sites - Commercial Hazardous Waste Operations

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — A Commercial Hazardous Waste Operation is a DEP primary facility type related to the Waste Management Hazardous Waste Program. The sub-facility types related to...

  12. Proposed Dry Storage Facility For ETRR-1 Spent Fuel

    International Nuclear Information System (INIS)

    A proposal is studied in an attempt to construct a dry storage of the spent fuel of the ETRR-1 reactor.The dry storage concept is chosen in order to minimize corrosion problems and water chemistry control needed for the wet storage. It is supposed that fuel elements taken from the core long time ago and undergone suitable activity and thermal decay in the present storage pool will be transferred to this dry storage. These will be placed in a steel lined holes in the storage. This storage is compact, making sure that the system remains sub-critical as well as verifying other safety requirements. The infinite multiplication factor should be less than (0.65), the value recommended by other authors. Subcriticality in the storage is assured by adjusting geometrical separation of the assemblies. The multiplication factor is calculated for different scenarios of fuel spacing and hole lining material. Also, it is assured that if the fuel storage is flooded with water, It will still be kept subcritical. The system will be ventilated, air pressure and radiation level will be monitored and controlled

  13. Safety analysis report for the mixed waste storage facility and portable storage units at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    The Mixed Waste Storage Facility (MWSF) including the Portable Storage Units (PSUs) is a government-owned contractor-operated facility located at the Idaho National Engineering Laboratory (INEL). Lockheed Martin Idaho Technologies Company (LMITCO) is the current operating contractor and facility Architect/Engineer as of September 1996. The operating contractor is referred to as open-quotes the Companyclose quotes or open-quotes Companyclose quotes throughout this document. Oversight of MWSF is provided by the Department of Energy Idaho Operations Office (DOE-ID). The MWSF is located in the Power Burst Facility (PBF) Waste Reduction Operations Complex (WROC) Area, approximately 10.6 km (6.6 mi) from the southern INEL boundary and 4 km (2.5 mi) from U.S. Highway 20

  14. Design Verification Report Neutron Radiography Facility (NRF) TRIGA Fuel Storage Systems

    International Nuclear Information System (INIS)

    This report outlines the methods, procedures, and outputs developed during the Neutron Radiography Facility (NRF) Training, Research and Isotope Production, General Atomics (TRIGA) fuel storage system design and fabrication

  15. Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

    International Nuclear Information System (INIS)

    The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

  16. Lawrence Livermore National Laboratory Decontamination and Waste Treatment Facility: Documentation of impact analysis for design alternatives presented in the Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    Lawrence Livermore National Laboratory (LLNL) is proposing to construct and operate a new Decontamination and Waste Treatment Facility (DWTF). The proposed DWTF would replace the existing Hazardous Waste Management (HWM) facilities at LLNL. The US Department of Energy (DOE) is preparing a Draft Environmental Impact Statement (DEIS) to assess the environmental consequences of the proposed DWTF and its alternatives. This report presents the assumptions, methodologies, and analyses used to estimate the waste flows, air emissions, ambient air quality impacts, and public health risks that are presented in the DEIS. Two DWTF design alternatives (Level I and Level II) have been designated as reasonable design alternatives considering available technologies, environmental regulations, and current and future LLNL waste generation. Both design alternatives would include new, separate radioactive and nonradioactive liquid waste treatment systems, a solidification unit, a new decontamination facility, storage and treatment facilities for reactive materials, a radioactive waste storage area, receiving and classification areas, and a uranium burn pan. The Level I design alternative would include a controlled-air incinerator system, while the Level II design alternative would include a rotary kiln incinerator system. 43 refs., 4 figs., 24 tabs

  17. Impact evaluation of sea salt aerosol given to nuclear spent fuel intermediate storage facility

    International Nuclear Information System (INIS)

    Nuclear spent fuel intermediate storage facility is planned to be located in the Sea of Japan coast area for the reasons of nuclear spent fuel transportation. Therefore, there is the risk of structure corrosion by an environmental pollution factor e.g. sea salt aerosol. This study is the corrosion risk evaluation of nuclear spent fuel storage facility by measuring the amount of sea salt aerosol coming. This study develops the new method to improve of the conventional JIS method. (author)

  18. A free-piston Stirling engine/linear alternator controls and load interaction test facility

    Science.gov (United States)

    Rauch, Jeffrey S.; Kankam, M. David; Santiago, Walter; Madi, Frank J.

    1992-08-01

    A test facility at LeRC was assembled for evaluating free-piston Stirling engine/linear alternator control options, and interaction with various electrical loads. This facility is based on a 'SPIKE' engine/alternator. The engine/alternator, a multi-purpose load system, a digital computer based load and facility control, and a data acquisition system with both steady-periodic and transient capability are described. Preliminary steady-periodic results are included for several operating modes of a digital AC parasitic load control. Preliminary results on the transient response to switching a resistive AC user load are discussed.

  19. A passive air-cooled dry storage facility for vitrified high-level wastes

    International Nuclear Information System (INIS)

    A conceptual design of air-cooled dry storage vault facility for vitrified high-level waste (HLW) canisters is developed for a site in northern Japan. The facility is designed for the reception and unloading of shielded seagoing transportation casks of vitrified HLW canisters, for the inspection of these canisters, and for their temporary storage for a period of up to 50 years. The waste is to be at least 9 years old when received, and the facility will be capable of storing up to 2,500 canisters. This paper provides a conceptual design to identify construction requirements, materials, and space requirements that are unique to the vitrified HLW storage facility. It also identifies the types of special systems and equipment needed in such a facility

  20. Impacts of ramping inflexibility of conventional generators on strategic operation of energy storage facilities

    DEFF Research Database (Denmark)

    Nasrolahpour, Ehsan; Kazempour, Jalal; Zareipour, Hamidreza;

    2016-01-01

    This paper proposes an approach to assist a pricemaker merchant energy storage facility in making its optimal operation decisions. The facility operates in a pool-based electricity market, where the ramping capability of other resources is limited. Also, wind power resources exist in the system....... The merchant facility seeks to maximize its profit through strategic inter-temporal arbitrage decisions, when taking advantage of those ramp limitations. The market operator, on the other hand, aims at maximizing the social welfare under wind power generation uncertainty. Thus, a stochastic bi......-level optimization model is proposed, taking into account the interactions between the storage facility and the market operator, and the existing market opportunities for the storage facility. The proposed bilevel model is then transformed into a Mathematical Program with Equilibrium Constraints (MPEC) that can be...

  1. Experiments of natural convection to evaluate heat transfer in the spent fuel dry storage facilities

    International Nuclear Information System (INIS)

    This paper describes heat transfer characteristics of natural convection in three kinds of storage facility: cask, vault and silo systems. Experiments of measuring velocity and temperature profiles in the boundary layer were performed. With these results, the performance of each storage containers been evaluated. (author)

  2. Durability of spent nuclear fuels and facility components in wet storage

    International Nuclear Information System (INIS)

    Wet storage continues to be the dominant option for the management of irradiated fuel elements and assemblies (fuel units). Fuel types addressed in this study include those used in: power reactors, research and test reactors, and defence reactors. Important decisions must be made regarding acceptable storage modes for a broad variety of fuel types, involving numerous combinations of fuel and cladding materials. A broadly based materials database has the following important functions: to facilitate solutions to immediate and pressing materials problems; to facilitate decisions on the most effective long term interim storage methods for numerous fuel types; to maintain and update a basis on which to extend the licenses of storage facilities as regulatory periods expire; to facilitate cost-effective transfer of numerous fuel types to final disposal. Because examinations of radioactive materials are expensive, access to materials data and experience that provide an informed basis to analyse and extrapolate materials behaviour in wet storage environments can facilitate identification of cost-effective approaches to develop and maintain a valuable materials database. Fuel storage options include: leaving the fuel in wet storage, placing the fuel in canisters with cover gases, stored underwater, or transferring the fuel to one of several dry storage modes, involving a range of conditioning options. It is also important to anticipate the condition of the various materials as periods of wet storage are extended or as decisions to transfer to dry storage are implemented. A sound basis for extrapolation is needed to assess fuel and facility component integrity over the expected period of wet storage. A materials database also facilitates assessment of the current condition of specific fuel and facility materials, with minimal investments in direct examinations. This report provides quantitative and semi-quantitative data on materials behaviour or references sources of data to

  3. Seismic evaluation of underground facilities for nuclear waste storage

    International Nuclear Information System (INIS)

    The underground facilities of the Waste Isolation Pilot Plant (WIPP) will be located in New Mexico salt formations. These facilities include multiple unlined drifts (unlined tunnels) 2,200 feet below the surface and four vertical shafts connecting the surface facilities and the drifts. The objective of this study is to determine whether the current designs for the WIPP underground facilities are adequate to withstand the effects of two postulated seismic events without failure as defined by performance assessment criteria. The first postulated earthquake is based on the requirements of the Uniform Building Code (UBC-1979) for Zone 1. The second is based on a Design Basis Earthquake

  4. Cooperative Optimal Operation of Wind-Storage Facilities

    DEFF Research Database (Denmark)

    Farashbashi-Astaneh, Seyed-Mostafa; Hu, Weihao; Chen, Zhe

    2014-01-01

    As the penetration of wind power increases in power systems across the world, wind forecast errors become an emerging problem. Storage units are reliable tools to be used in cooperation with wind farms to mitigate imbalance penalties. Nevertheless they are not still economically viable due to huge...... investment cost. We suggest benefitting the storage unit as a regulation service provider beside its normal operation for mitigating wind power imbalances. This idea comes from the fact that storage units have a fast ramping capability which is necessary to meet close to real-time regulation needs. In this...... paper a framework is proposed to formulate the optimal design of storage unit’s operation under different scenarios. These scenarios include whether the wind farm is actually generating more or less than the scheduled level submitted to day-ahead market. The results emphasize that the deployment of...

  5. Design Alternatives for a Free Electron Laser Facility

    Energy Technology Data Exchange (ETDEWEB)

    Jacobs, K; Bosch, R A; Eisert, D; Fisher, M V; Green, M A; Keil, R G; Kleman, K J; Kulpin, J G; Rogers, G C; Wehlitz, R; Chiang, T; Miller, T J; Lawler, J E; Yavuz, D; Legg, R A

    2012-07-01

    The University of Wisconsin-Madison is continuing design efforts for a vacuum ultraviolet/X-ray Free Electron Laser facility. The design incorporates seeding the FEL to provide fully coherent photon output at energies up to {approx}1 keV. The focus of the present work is to minimize the cost of the facility while preserving its performance. To achieve this we are exploring variations in the electron beam driver for the FEL, in undulator design, and in the seeding mechanism. Design optimizations and trade-offs between the various technologies and how they affect the FEL scientific program will be presented.

  6. Final environmental assessment and Finding-of-No-Significant-Impact - drum storage facility for interim storage of materials generated by environmental restoration operations

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has prepared an Environmental Assessment (EA), DOE/EA-0995, for the construction and operation of a drum storage facility at Rocky Flats Environmental Technology Site, Golden, Colorado. The proposal for construction of the facility was generated in response to current and anticipated future needs for interim storage of waste materials generated by environmental restoration operations. A public meeting was held on July 20, 1994, at which the scope and analyses of the EA were presented. The scope of the EA included evaluation of alternative methods of storage, including no action. A comment period from July 5, 1994 through August 4, 1994, was provided to the public and the State of Colorado to submit written comment on the EA. No written comments were received regarding this proposed action, therefore no comment response is included in the Final EA. Based on the analyses in the EA, DOE has determined that the proposed action would not significantly affect the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an Environmental Impact Statement is not required and the Department is issuing this Finding of No Significant Impact

  7. Thermal Energy Storage in Molten Salts: Overview of Novel Concepts and the DLR Test Facility (TESIS)

    OpenAIRE

    Breidenbach, Nils; Martin, Claudia; Jockenhöfer, Henning; Bauer, Thomas

    2016-01-01

    At present, two-tank molten salt storage systems are the established commercially available concept for solar thermal power plants. Due to their very low vapour pressure and comparatively high thermal stability, molten salts are preferred as the heat transfer fluid and storage medium. Therefore, the development of alternative, more cost-effective concepts is an important step in making thermal energy storage more competitive for industrial processes and solar thermal applications. The pape...

  8. A modular vault dry storage facility for Fort St Vrain

    International Nuclear Information System (INIS)

    GEC-Alsthom's Modular Vault Dry Store offers an economical, self-contained means of storing relatively small quantities of spent fuel at a plant site. Its first application will be at Fort St Vrain (USA), where a facility is due to be commissioned in 1992. The main features of the facility are described. (author)

  9. GNS Experience on the Long-Term Storage at Dry Interim Storage Facilities Especially in Ahaus and Gorleben

    International Nuclear Information System (INIS)

    This presentation provides a general overview on the operation experience of the dry interim storage facilities in Ahaus and Gorleben (later referred to as TBL-A and TBL-G). GNS is solely in charge of the operation and maintenance of both facilities licensed for a dry storage period of 40 years. The amount of different cask types stored to date which are loaded with spent fuel and reprocessing waste and the cask specific information such as heat capacity, heat flow and dose rate are shown. A presentation of the transport and storage operation experience (e. g. statistics of the monitoring system) follows as well as an outlook on future activities. The associated licensing procedures are outlined in view of pre-existing licenses together with present or future licensing activities. This includes cask approval procedures according to the international safety requirements for transport and licensing procedures as laid down in the German Atomic Act. Both facilities have been operated, to a large extent, independently of nuclear power plants. Different casks have been stored there for more than ten years. In terms of best practices the vast operational experience gathered at these interim storage facilities is shown on practical examples i.e. the 10-year cask inspection, the pilot process for the periodical safety review as well as the ageing management demonstrating the robustness of the dry cask storage concept. The key aspects of the GNS expertise and a summary of the GNS position as well as perspectives for the long-term dry storage complete the presentation. (authors)

  10. Hazard categorization and baseline documentation for the Sodium Storage Facility. Revision 1

    International Nuclear Information System (INIS)

    Hazard Categorization evaluation has been performed in accordance with DOE-STD-1027 for the Sodium Storage Facility at FFTF and a determination of less than Category 3 or non-nuclear has been made. Hazard Baseline Documentation has been performed in accordance with DOE-EM-STD-5502 and a determination of ''Radiological Facility'' has been made

  11. Overview of the Spent Nuclear Fuel Storage Facilities at the Savannah River Site. Revision 1

    International Nuclear Information System (INIS)

    This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels and L-Basin facilities. This paper provides a useful reference to foreign facilities, cask owners and shipping contractors on the cask and fuel handling capabilities of the Savannah River Site

  12. Risk-oriented approach for assessing the environmental safety of radioactive waste storage facilities

    International Nuclear Information System (INIS)

    The article discusses the risk-oriented approach for assessing the ecological security of radioactive waste storage facilities. On the basis of probability indicators the condition of ecological safety is found to be met at Odessa State Multiregional Facility on the normative criteria of deaths

  13. Radioactive waste storage facility and underground disposal method for radioactive wastes using the facility

    International Nuclear Information System (INIS)

    A sealed container storage chamber is formed in underground rocks. A container storage pool is formed on the inner bottom of the sealed vessel storage chamber. A heat exchanger for cooling water and a recycling pump are disposed on an operation floor of the sealed vessel storage chamber. Radioactive wastes sealed vessels in which radioactive wastes are sealed are transferred from the ground to the sealed vessel storage chamber through a sealed vessel transferring shaft, and immersed in cooling water stored in the vessel storage pool. When after heat of the radioactive wastes is removed by the cooling water, the cooling water in the vessel storage pool is sucked up to the ground surface. After dismantling equipments, bentonite-type fillers are filled in the inside of the sealed vessel storage chamber, sealed vessel transferring shaft, air supplying shaft and air exhaustion shaft, and the radioactive waste-sealed vessels can be subjected stably to into underground disposal. (I.N.)

  14. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear and Industrial Safety Agency (NISA: which prepares necessary regulations for Spent Fuel Interim Storage Facilities). In 2010 fiscal year, JNES completed technical evaluation of the standard (prepared by Atomic Energy Society of Japan) used for the storage facility (dual purpose cask system) being constructed in Mutsu-City and R and D for UT test of welded canister lids which is required for concrete cask storage facilities. And also, JNES is preparing dynamic test of spent fuel to examine the integrity of spent fuel at cask drop accidents and PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. The results of these tests will be reported in 2011 and 2012 fiscal year. (author)

  15. Selection of away-from-reactor facilities for spent fuel storage. A guidebook

    International Nuclear Information System (INIS)

    This publication aims to provide information on the approaches and criteria that would have to be considered for the selection of away-from-reactor (AFR) type spent fuel storage facilities, needs for which have been growing in an increasing number of Member States producing nuclear power. The AFR facilities can be defined as a storage system functionally independent of the reactor operation providing the role of storage until a further destination such as a disposal) becomes available. Initially developed to provide additional storage space for spent fuel, some AFR storage options are now providing additional spaces for extended storage of spent fuel with a prospect for long term storage, which is becoming a progressive reality in an increasing number of Member States due to the continuing debate on issues associated with the endpoints for spent fuel management and consequent delays in the implementation of final steps, such as disposal. The importance of AFR facilities for storage of spent fuel has been recognized for several decades and addressed in various IAEA publications in the area of spent fuel management. The Guidebook on Spent Fuel Storage (Technical Reports Series No. 240 published in 1984 and revised in 1991) discusses factors to be considered in the evaluation of spent fuel storage options. A technical committee meeting (TCM) on Selection of Dry Spent Fuel Storage Technologies held in Tokyo in 1995 also deliberated on this issue. However, there has not been any stand-alone publication focusing on the topic of selection of AFR storage facilities. The selection of AFR storage facilities is in fact a critical step for the successful implementation of spent fuel management programmes, due to the long operational periods required for storage and fuel handling involved with the additional implication of subsequent penalties in reversing decisions or changing the option mid-stream especially after the construction of the facility. In such a context, the long

  16. Gas Test Loop Facilities Alternatives Assessment Report Rev 1

    Energy Technology Data Exchange (ETDEWEB)

    William J. Skerjanc; William F. Skerjanc

    2005-07-01

    An important task in the Gas Test Loop (GTL) conceptual design was to determine the best facility to serve as host for this apparatus, which will allow fast-flux neutron testing in an existing nuclear facility. A survey was undertaken of domestic and foreign nuclear reactors and accelerator facilities to arrive at that determination. Two major research reactors in the U.S. were considered in detail, the Advanced Test Reactor (ATR) and the High Flux Isotope Reactor (HFIR), each with sufficient power to attain the required neutron fluxes. HFIR routinely operates near its design power limit of 100 MW. ATR has traditionally operated at less than half its design power limit of 250 MW. Both of these reactors should be available for at least the next 30 years. The other major U.S. research reactor, the Missouri University Research Reactor, does not have sufficient power to reach the required neutron flux nor do the smaller research reactors. Of the foreign reactors investigated, BOR-60 is perhaps the most attractive. Monju and BN 600 are power reactors for their respective electrical grids. Although the Joyo reactor is vigorously campaigning for customers, local laws regarding transport of radioactive material mean it would be very difficult to retrieve test articles from either Japanese reactor for post irradiation examination. PHENIX is scheduled to close in 2008 and is fully booked until then. FBTR is limited to domestic (Indian) users only. Data quality is often suspect in Russia. The only accelerator seriously considered was the Fuel and Material Test Station (FMTS) currently proposed for operation at Los Alamos National Laboratory. The neutron spectrum in FMTS is similar to that found in a fast reactor, but it has a pronounced high-energy tail that is atypical of fast fission reactor spectra. First irradiation in the FMTS is being contemplated for 2008. Detailed review of these facilities resulted in the recommendation that the ATR would be the best host for the GTL.

  17. Screening and identification of sites for a proposed Monitored Retrievable Storage Facility

    International Nuclear Information System (INIS)

    The Director, Office of Civilian Radioactive Waste Management (OCRWM), Department of Energy (DOE), has identified the Clinch River Breeder Reactor site, the DOE Oak Ridge Reservation and the Tennessee Valley Authority (TVA) Hartsville Nuclear Plant site as preferred and alternative sites, respectively, for development of site-specific designs as part of the proposal for construction of an integrated Monitored Retrievable Storage (MRS) Facility. The proposal, developed pursuant to Section 141 (b) of the Nuclear Waste Policy Act of 1982, will be submitted to Congress in January 1986. The Director expects to propose to Congress that an MRS be constructed at the perferred site. His judgment could change based on information to be developed between now and January 1986. The decision to construct an MRS facility and final site selection are reserved by Congress for itself. The Director's judgment is based on the results of a rigorous site screening and evaluation process described in this report. The three sites were selected from among eleven sites evaluated in detail. The Clinch River Breeder Reactor site, owned by the Tennessee Valley Authority, was identified as the preferred site. It has several particularly desirable features including: (1) federal ownership and control by the Department of Energy; (2) particularly good transportation access (five miles to the nearest interstate highway and direct rail access); (3) site characteristics and current data base judged by the NRC in 1983 as sufficient for granting a limited work authorization for the now cancelled breeder reactor; and (4) a technical community in the vicinity of site which can provide experienced nuclear facility support functions. 6 figs., 2 tabs

  18. Optimal control of hydroelectric facility incorporating pump storage

    International Nuclear Information System (INIS)

    We consider a simple model of a pump-assisted hydroelectric facility operating in a market with time-varying but deterministic power prices and constant water inflows. The engineering details of the facility are described by a model containing several parameters. We present an algorithm for optimizing first the energy and then the profit produced by these plants. This algorithm allows us to describe the relationships between control trajectory and time, and between inflow and price. Remarkably, we see that under some reasonable choices of facility parameters and for power prices that are not extremely variable, the optimal profit operation of these facilities is not too different from their optimal energy operation, and the control is less affected by the price as the inflow rate increases. (author)

  19. Safety evaluation of dry-cask storage facility for spent fuel during earthquake

    International Nuclear Information System (INIS)

    Design criteria of storage facilities were established considering the special circumstances of Japan, such as limited site area and strong earthquakes. Therefore, it is necessary to confirm the integrity in the rare case of the collapse of storage building and gantry crane, the cooling performance of cask buried in concrete rubbish, and the resistance for overture of dry storage cask during earthquake. This report evaluated the security for impact load of falling body such as concrete wall or gantry crane, the stability of the dry storage cask during earthquake, and the cooling performance of cask. (author)

  20. Study on heat removal system of dry storage facility for spent fuel

    International Nuclear Information System (INIS)

    Dry vault type is one of the interim dry storage systems that adopts a natural convection air cooling system, needs no active systems, and generates little radioactive waste. The maximum allowable temperature of fuel cladding was determined on the basis of creep strain criteria for a long term dry storage environment in order to avoid cladding degradation. It was necessary to establish an evaluation method of heat transfer inside and outside the fuel loaded canisters for the design of storage facility. Therefore, the experimental and analytical studies of heat transfer of the dry vault storage system were carried out using experimental apparatus and the analysis program based on the finite element method. (author)

  1. 77 FR 61633 - Information Collection: Renewable Energy and Alternate Uses of Existing Facilities on the Outer...

    Science.gov (United States)

    2012-10-10

    ... Bureau of Ocean Energy Management Information Collection: Renewable Energy and Alternate Uses of Existing... paperwork requirements in the regulations under ``Renewable Energy and Alternate Uses of Existing Facilities..., transportation, or transmission of energy from sources other than oil and gas (renewable energy)....

  2. 36 CFR 1234.30 - How does an agency request authority to establish or relocate records storage facilities?

    Science.gov (United States)

    2010-07-01

    ... authority to establish or relocate records storage facilities? 1234.30 Section 1234.30 Parks, Forests, and... RECORDS STORAGE FACILITIES Facility Approval and Inspection Requirements § 1234.30 How does an agency...” excludes NARA-owned and operated records centers. For purposes of this section and § 1234.34, the...

  3. 36 CFR 1234.12 - What are the fire safety requirements that apply to records storage facilities?

    Science.gov (United States)

    2010-07-01

    ... requirements that apply to records storage facilities? 1234.12 Section 1234.12 Parks, Forests, and Public... STORAGE FACILITIES Facility Standards § 1234.12 What are the fire safety requirements that apply to... reference, see § 1234.3). (e) The fire resistive rating of the roof must be a minimum of 1/2 hour for...

  4. Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

    International Nuclear Information System (INIS)

    On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

  5. The Study on Regulations of Interim Spent Fuel Storage Facility in Japan

    International Nuclear Information System (INIS)

    The expansion of nuclear power generation inevitably result in the increase of spent nuclear fuel generation. Every year ∼700t of spent nuclear fuels are accumulated and total of 10,761t of spent nuclear fuels generated from 20 reactors are stored within the reactor sites by the end of 2009. If this trend is maintained, it is expected that Korea will have ∼30,000t of spent nuclear fuel by 2030. The capacity of pools in reactor sites is expected to be reached from 2016 and Korea need to prepare measures including the introduction of interim storage facility urgently. Considering the domestic situation described so far, it is be very necessary to survey and analyze the regulations of interim storage facilities of advanced countries. This report excerpts and analyzes the report of Japanese Nuclear Energy Safety Organization (JNES) on the regulations of interim storage facilities which was issues before the construction of the Mutz Interim Storage Facility. This report will be effectively used for the preparation of interim storage facility of Korea

  6. Long term Integrity of Spent Fuel and Construction Materials and Behaviour of Components for Dry Storage Facilities

    International Nuclear Information System (INIS)

    In Japan, two dry storage facilities at TEPCO and JAPCO sites have been in operation since 1995 and 2002 respectively. The TEPCO dry storage facility was damaged by a Tsunami attack on 11th March 2011. The casks stored in the facility have since been moved to an onsite temporary cask custody area; after confirmation of the integrity of casks. On the other hand, the Tsunami did not attack the dry storage facility at the JAPCO site. The integrity of the storage building and the casks were maintained. In addition, an off-site centralized dry storage facility has been constructed at Mutsu City. Operation of the storage facility is pending a safety re-examination against new safety regulations. Its final storage capacity will be 5000 t(U) and the storage period is up to 50 years. To support storage operations, it is therefore necessary to obtain and evaluate data on the integrity of spent fuels and cask construction materials during long term dry storage. Objectives: Construction materials for dry storage facilities: • To evaluate long-term reliability of welded stainless steel canisters under stress corrosion cracking (SCC) environment, including the critical salt density deposited on the canister to initiate SCC, monitoring, prevention, and the mitigation method of SCC; • To detect and analyze the cover gas leak from canisters; • To evaluate integrity of sealability of metal gasket under long term storage; • To evaluate influence of the vibration on sealing performance of the ageing gasket

  7. Transfer station and storage facility for medium active solid waste

    International Nuclear Information System (INIS)

    In the Muehlheim Kaerlich nuclear power plant a temporary store has been erected for production-related medium active solid waste (MAW). This paper reports that the following were the main criteria behind this step: creating a temporary store capacity for specific MAW for the duration of the entire operating time, the temporary storage of MAW over several years to achieve an appropriate dose reduction (decay period), and market independence

  8. Groundwater Remediation and Alternate Energy at White Sands Test Facility

    Science.gov (United States)

    Fischer, Holger

    2008-01-01

    White Sands Test Facility Core Capabilities: a) Remote Hazardous Testing of Reactive, Explosive, and Toxic Materials and Fluids; b) Hypergolic Fluids Materials and Systems Testing; c) Oxygen Materials and System Testing; d) Hypervelocity Impact Testing; e)Flight Hardware Processing; and e) Propulsion Testing. There is no impact to any drinking water well. Includes public wells and the NASA supply well. There is no public exposure. Groundwater is several hundred feet below ground. No air or surface water exposure. Plume is moving very slowly to the west. Plume Front Treatment system will stop this westward movement. NASA performs on-going monitoring. More than 200 wells and zones are routinely sampled. Approx. 850 samples are obtained monthly and analyzed for over 300 different hazardous chemicals.

  9. Automated Storage Retrieval System (ASRS) Role Towards Achievement of Safety Objective and Safety Culture in Radioactive Storage Facilities

    International Nuclear Information System (INIS)

    Waste Technology Development Centre (WasTeC) has been awarded with quality management system ISO 9001:2000 in June 2004 or now known as ISO 9001:2008. The scope of the unit's ISO certification is radioactive waste management and storage of radioactive material. To meet the objectives and requirements ISO 9001:2008, WasTeC has started a project known as Automated Storage and Retrieval System (ASRS). ASRS is a computing controlled method for automatically depositing and retrieving waste from defined locations. The system is used to replace the existing process of storage and retrieval of radioactive waste at storage facility at block 33.The main objective of this project is to reduced the radiation exposure to the worker and potential forklift accident occur during storage and retrieval of the radioactive waste. By using the ASRS system, WasTeC/ Nuclear Malaysia can provide a safe storage of radioactive waste and the use of this system can eliminate the repeat handling and can improve productivity. (author)

  10. Conceptual design of interim storage facility for CNAI

    International Nuclear Information System (INIS)

    The reduced storage capacity available in the two spent fuel pools of argentine PHWR Atucha-1 power plant, the current plans for extending the reactor operation beyond its design lifetime, and the government decision on Atucha-2 NPP construction ending, have motivated the evaluation of a dry storage option for the interim management of spent fuel assemblies. Two different designs are presently being analyzed by an expert working group, from both technical and economical points of views. Authors are proposing a modular system consisting of an arrangement of reinforced concrete structures into which welded metallic canisters loaded with 37 spent fuel assemblies each stored in horizontal position. The reinforced concrete module is designed to provide the necessary physical protection and biological shielding to the loaded canisters during long-term storage, as well as passive means to remove the spent fuel decay heat by a combination of radiation, conduction and natural air convection. In this works are presented advances in the conceptual designs for a spent nuclear fuel system to Atucha I nuclear power plant. (author)

  11. Transuranic waste storage and assay facility (TRUSAF) interim safety basis

    International Nuclear Information System (INIS)

    The TRUSAF ISB is based upon current facility configuration and procedures. The purpose of the document is to provide the basis for interim operation or restrictions on interim operations and the authorization basis for the TRUSAF at the Hanford Site. The previous safety analysis document TRUSAF hazards Identification and Evaluation (WHC 1977) is superseded by this document

  12. Improving aircraft accident forecasting for an integrated plutonium storage facility

    International Nuclear Information System (INIS)

    Aircraft accidents pose a quantifiable threat to facilities used to store and process surplus weapon-grade plutonium. The Department of Energy (DOE) recently published its first aircraft accident analysis guidelines: Accident Analysis for Aircraft Crash into Hazardous Facilities. This document establishes a hierarchy of procedures for estimating the small annual frequency for aircraft accidents that impact Pantex facilities and the even smaller frequency of hazardous material released to the environment. The standard establishes a screening threshold of 10-6 impacts per year; if the initial estimate of impact frequency for a facility is below this level, no further analysis is required. The Pantex Site-Wide Environmental Impact Statement (SWEIS) calculates the aircraft impact frequency to be above this screening level. The DOE Standard encourages more detailed analyses in such cases. This report presents three refinements, namely, removing retired small military aircraft from the accident rate database, correcting the conversion factor from military accident rates (accidents per 100,000 hours) to the rates used in the DOE model (accidents per flight phase), and adjusting the conditional probability of impact for general aviation to more accurately reflect pilot training and local conditions. This report documents a halving of the predicted frequency of an aircraft impact at Pantex and points toward further reductions

  13. Understanding and managing aging ar fuel and facility components in wet storage

    International Nuclear Information System (INIS)

    Full text: Numerous nuclear fuel storage facilities have been challenged by the need to operate longer than originally intended. Several circumstances contribute to the need to extend periods of storage facility operations, including delays in availability of permanent repositories, delays or cancellation of fuel reprocessing capacities, and, in some countries, decisions to operate nuclear plants beyond the original license period. Aging is a term that has emerged to focus attention on potential consequences of extended operation on the structures, systems, and components (SSCs) that comprise the facilities. Time related degradation of materials that may occur in extended operation needs systematic consideration and mitigation. Facility staffs that do not effectively consider effects of aging are likely to react to materials failures rather than to anticipate and mitigate them. Examples of Age-Related Degradation in Nuclear Fuel Storage Facilities are given in the paper. Predominantly, nuclear fuel storage facilities operate with minimal impacts of age-related degradation. However, review of cases involving degradation of materials provides guidance regarding situations that should be avoided. Included in the paper will be reference to cases of materials degradation in storage, including the following: pitting corrosion of aluminum alloys; intergranular stress corrosion cracking of sensitized stainless steels; corrosion of carbon steels; uranium metal corrosion; deterioration of some neutron absorbers. The concepts of understanding and managing aging provide bases for systematic consideration of the range of facility materials and environments that need assessment to anticipate impacts of aging on the SSCs. Several national and international organizations have provided comprehensive and systematic guidance regarding how to implement effective aging management in nuclear facilities, notably the International Atomic Energy Agency (IAEA) and the US Nuclear Regulatory

  14. Studies and research concerning BNFP: converting reprocessing plant's fuel receiving and storage area to an away-from-reactor (AFR) storage facility. Final report

    International Nuclear Information System (INIS)

    Converting a reprocessing plant's fuel receiving and storage station into an Away-From-Reactor storage facility is evaluated in this report. An engineering analysis is developed which includes (1) equipment modifications to the facility including the physical protection system, (2) planning schedules for licensing-related activities, and (3) cost estimates for implementing such a facility conversion. Storage capacities are evaluated using the presently available pools of the existing Barnwell Nuclear Fuel Plant-Fuel Receiving and Storage Station (BNFP-FRSS) as a model

  15. Interim nuclear spent fuel storage facility - From complete refusal to public acceptance

    International Nuclear Information System (INIS)

    Full text: As usual in P.R., there was a complicated, politically sensitive situation we had to face at the beginning and it wasn't easy to create the right P.R. programme with the right targets: CEZ needed a new storage facility for the nuclear spent fuel from its two NPPs - Dukovany and Temelin. Firstly, CEZ preferred to build an on-site facility for the Dukovany NPP to last until the year 2004; secondly, a facility for the Temelin NPP several years later. But the Czech Government decided to limit Dukovany's storage capacity during a public discussion in 1992. Therefore, at the end of 1993, CEZ started the site selection process for a central storage facility targeted at ten regions in the country. In P.R. we decided on two main goals: 1. To gain public acceptance of a central storage facility at least at one site, and hopefully at more. 2. To change public opinion (especially around the Dukovany NPP) in order to create the proper atmosphere for changing the government's decision to limit storage capacity. We wanted to prove that we could choose the fight technical and economical solution without political limits. This obviously presented a challenge as it would be problematic for CEZ to be very visible in the campaign: We wanted people to know that the government had made a bad decision, but we also had to make it clear that our objections were based not on questions of momentary corporate advantage but instead on solid technical grounds. Most would only see self interest. We wanted to show them the facts. Of course, some times it wasn't easy to hit both targets at the same time. There was a lot of hard work in the middle. We gained new experience and we learned a lot trying to get public confidence in nuclear safety, in our company's reliability and in some local profits for a storage site: Firstly none of those regions was excited by the idea o a storage facility in its backyard. Most of them were very strongly and actively against it and did not want to

  16. Storage facilities for radioactive waste in tertiary education environment

    International Nuclear Information System (INIS)

    The research and teaching endeavors of the university environment generate an assortment of radioactive waste that is unique in the range of isotopes and activities present, although the physical quantities of the waste may not be large. Universities may also be subject to unexpected, close public scrutiny of their operations due to the diverse nature of the university campus. This is rarely the case for other generators of radioactive waste. The experience of Monash University in formulating solutions for long term storage of radioactive waste is examined with respect to design, location and administration of the waste stores that were finally constructed. 7 refs., 1 tab., 1 fig

  17. [Alternative treatment in psychiatric and psychotherapy facilities in Germany].

    Science.gov (United States)

    Andritzky, W

    1996-01-01

    Questionnaires were sent to 545 clinics with at least partial psychotherapeutic or psychiatric activities to find out the spectrum of therapeutic techniques and methods used, as well as the spectrum of therapists' qualifications. From the 314 responding clinics, 127 different methods were named with an average of 4.0 each. The proportion of physicians and psychologists to patients becomes worse the bigger the clinics are: e.g., in the class of less than 50 beds, one psychologist cares for 7 patients; in the class 51-300 beds, the relation is one to 48. The six most frequently used methods are: music therapy (36.9%), imagery (25.2%), dance therapy (23.2%), autogenous training (22.6%), body therapies (21.7%), and psychodrama (18.2%). Apart from physicians and psychologists, 38 other professional groups were named. Comparing the answers concerning the methods with the performing professional group, an apparent trend towards a professional diversification was found, e.g. only 62% of music therapy is performed by music therapists, the rest by other professional groups. Finally, analysis of special remarks on the questionnaires resulted in four groups: discussions concerning the term alternative methods, recommendations to use unconventional methods after the clinical phase, conceptual changes of a clinic, and broader theoretical backgrounds integrating various methods, e.g. the psychoanalytic concept. PMID:8851128

  18. Design report for the interim waste containment facility at the Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection

  19. Monitoring plan for routine organic air emissions at the Radioactive Waste Management Complex Waste Storage Facilities

    International Nuclear Information System (INIS)

    This monitoring plan provides the information necessary to perform routine organic air emissions monitoring at the Waste Storage Facilities located at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The Waste Storage Facilities include both the Type I and II Waste Storage Modules. The plan implements a dual method approach where two dissimilar analytical methodologies, Open-Path Fourier Transform Infrared Spectroscopy (OP-FTIR) and ancillary SUMMA reg-sign canister sampling, following the US Environmental Protection Agency (EPA) analytical method TO-14, will be used to provide qualitative and quantitative volatile organic concentration data. The Open-Path Fourier Transform Infrared Spectroscopy will provide in situ, real time monitoring of volatile organic compound concentrations in the ambient air of the Waste Storage Facilities. To supplement the OP-FTIR data, air samples will be collected using SUMMA reg-sign, passivated, stainless steel canisters, following the EPA Method TO-14. These samples will be analyzed for volatile organic compounds with gas chromatograph/mass spectrometry analysis. The sampling strategy, procedures, and schedules are included in this monitoring plan. The development of this monitoring plan is driven by regulatory compliance to the Resource Conservation and Recovery Act, State of Idaho Toxic Air Pollutant increments, Occupational Safety and Health Administration. The various state and federal regulations address the characterization of the volatile organic compounds and the resultant ambient air emissions that may originate from facilities involved in industrial production and/or waste management activities

  20. COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA

    International Nuclear Information System (INIS)

    Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal

  1. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    International Nuclear Information System (INIS)

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  2. Safety report for Central Interim Storage facility for radioactive waste from small producers

    International Nuclear Information System (INIS)

    In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage (CIS) in Brinje, intended only for radioactive waste from industrial, medical and research applications. With the transfer of the responsibilities for the storage operation, ARAO, the new operator of the facility, received also the request from the Slovenian Nuclear Safety Administration for refurbishment and reconstruction of the storage and for preparation of the safety report for the storage with the operational conditions and limitations. In order to fulfill these requirements ARAO first thoroughly reviewed the existing documentation on the facility, the facility itself and the stored inventory. Based on the findings of this review ARAO prepared several basic documents for improvement of the current conditions in the storage facility. In October 2000 the Plan for refurbishment and modernization of the CIS was prepared, providing an integral approach towards remediation and refurbishment of the facility, optimization of the inventory arrangement and modernization of the storage and storing utilization. In October 2001 project documentation for renewal of electric installations, water supply and sewage system, ventilation system, the improvements of the fire protection and remediation of minor defects discovered in building were completed according to the Act on Construction. In July 2003 the safety report was prepared, based on the facility status after the completion of the reconstruction works. It takes into account all improvements and changes introduced by the refurbishment and reconstruction of the facility according to project documentation. Besides the basic characteristics of the location and its surrounding, it also gives the technical description of the facility together with proposed solutions for the renewal of electric installations, renovation of water supply and sewage system, refurbishment of the ventilation system, the improvement of fire

  3. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    International Nuclear Information System (INIS)

    This document describes the hazards and operability (HAZOP) analysis performed for the activities associated with the storage of Spent Nuclear Fuel (SNF) sludge at the T Plant. The safety authorization basis for the T Plant for SNF sludge storage is defined as those aspects of facility design and operational requirements relied upon by DOE to authorize operations. The safety authorization basis for the current T Plant activities is described in HNF-SD-WM-ISB-006, Rev 2, ''Interim Safety Basis for Solid Waste Facilities (T Plant) (ISB)'' and associated amendments and engineering change notices. In addition the authorization basis includes other document as summarized in Section 1.3

  4. Decontamination of transport casks and of spent fuel storage facilities

    International Nuclear Information System (INIS)

    The present document provides an analysis of the technical papers presented at the meeting as well as a summary of the panel discussion. Conclusions and Recommendations: The meeting agreed that the primary source of contamination of transport casks is the production of radioactive isotopes in nuclear fuel and activation products of fuel components in nuclear reactors. The type, amount of mechanism for the release of these isotopes depend on the reactor type and fuel handling process. The widespread use of pools for the storage and handling of fuel provides an easy path for the transfer of contamination. Control of pool water conditions is essential for limiting the spread of contamination. For plants where casks are immersed in pools for loading, the immersion times should be minimised. Casks should be designed for ease of decontamination. The meeting discussed the use of stainless steel and suitable paints for coating casks. Designers should consider the appropriate coating for specific applications. The use of pressurized water for decontamination is recommended whenever possible. A number of commercially available reagents exist for decontaminating cask external surfaces. More work, however, is needed to cope with Pressurized Water Reactor crud within casks. Leaking fuel should be identified and isolated before storage in pools. Basic studies of the uptake and release of contamination from cask surfaces should be initiated. Standardization of methods of contamination measurement and instrumentation should be instituted. Refs, figs and tabs

  5. Long term integrity of spent fuel and construction materials for dry storage facilities

    International Nuclear Information System (INIS)

    In Japan, two dry storage facilities at reactor sites have already been operating since 1995 and 2002, respectively. Additionally, a large scale dry storage facility away from reactor sites is under safety examination for license near the coast and desired to start its operation in 2010. Its final storage capacity is 5,000tU. It is therefore necessary to obtain and evaluate the related data on integrity of spent fuels loaded into and construction materials of casks during long term dry storage. The objectives are: - Spent fuel rod: To evaluate hydrogen migration along axial fuel direction on irradiated claddings stored for twenty years in air; To evaluate pellet oxidation behaviour for high burn-up UO2 fuels; - Construction materials for dry storage facilities: To evaluate long term reliability of welded stainless steel canister under stress corrosion cracking (SCC) environment; To evaluate long term integrity of concrete cask under carbonation and salt attack environment; To evaluate integrity of sealability of metal gasket under long term storage and short term accidental impact force.

  6. Resource Conservation and Recovery Act Closure Plan for the Y-12 9409-5 Tank Storage Facility

    International Nuclear Information System (INIS)

    This document presents information on the closure of the Y-12 9409-5 Tank Storage Facility. Topics discussed include: facility description; closure history; closure performance standard; partial closure; maximum waste inventory; closure activities; schedule; and postclosure care

  7. Monitored retrievable storage submission to Congress: Volume 2, Environmental assessment for a monitored retrievable storage facility. [Contains glossary

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-02-01

    This Environmental Assessment (EA) supports the DOE proposal to Congress to construct and operate a facility for monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portion of Oak Ridge, Tennessee. The first part of this document is an assessment of the value of, need for, and feasibility of an MRS facility as an integral component of the waste management system. The second part is an assessment and comparison of the potential environmental impacts projected for each of six site-design combinations. The MRS facility would be centrally located with respect to existing reactors, and would receive and canister spent fuel in preparation for shipment to and disposal in a geologic repository. 207 refs., 57 figs., 132 tabs.

  8. Quality Assurance Program Plan (QAPP) Waste Encapsulation and Storage Facility (WESF)

    International Nuclear Information System (INIS)

    This Quality Assurance Plan describes how the Waste Encapsulation and Storage Facility (WESF) implements the quality assurance (QA) requirements of the Quality Assurance Program Description (QAPD) (HNF-Mp-599) for Project Hanford activities and products. This QAPP also describes the organizational structure necessary to successfully implement the program. The QAPP provides a road map of applicable Project Hanford Management System Procedures, and facility specific procedures, that may be utilized by WESF to implement the requirements of the QAPD

  9. Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)

    International Nuclear Information System (INIS)

    This Waste Encapsulation Storage Facility (WESF) Dangerous Waste Training Plan (DWTP) applies to personnel who perform work at, or in support of WESF. The plan, along with the names of personnel, may be given to a regulatory agency inspector upon request. General workers, subcontractors, or visiting personnel who have not been trained in the management of dangerous wastes must be accompanied by an individual who meets the requirements of this training plan. Dangerous waste management includes handling, treatment, storage, and/or disposal of dangerous and/or mixed waste. Dangerous waste management units covered by this plan include: less-than-90-day accumulation area(s); pool cells 1-8 and 12 storage units; and process cells A-G storage units. This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units and the Less-than-90-Day Accumulation Areas

  10. Engineering program in order to increase the irradiated fuel storage capacity in pool facilities of Juragua

    International Nuclear Information System (INIS)

    In 1993, a technical program in the spent fuel storage area of Nuclear Plant Juragua was launched. Such a program tries to carry out an engineering assessment of the possibility of increasing the spent fuel storage capacity in pool storage facilities by using high density racks (re-racking) instead of the original (non-compact) ones. The purpose of the above-mentioned program is to evaluate possible solutions that can be applied to the construction works prior to plant operation. The first stage of the program for the 1994-95 period is an ongoing Engineering-Economic Feasibility Study (EEFS), which endeavors to examine the capabilities of the reloading pool in Unit-1 Reactor building and long-term storage pool in auxiliary building in high density storage conditions. Technical details of the EEFS and reached results and difficulties are described. (author). 5 refs., 2 figs

  11. Development of Aircraft Impact Scenario on a Concrete Cask in Interim Storage Facility

    International Nuclear Information System (INIS)

    This paper provides a method for determining the failure criteria in global and local damage responses for the concrete cask under extreme mechanical impact condition. IAEA safety guide No. SSG-15 mentions the hypothetical initiating events of SNF storage. Among the external initiating events, the aircraft strike on a storage cask is considered one of the dominant contributions to the risk during storage phase. Although the probability of aircraft crash on ISF is extremely small, it is important to develop the accident scenario caused by an intentional malicious acts launched towards the storage facility in terms to improve inherent security. Thus, the probabilistic approach to develop aircraft impact scenarios on a storage cask is needed

  12. Retrieval of fluidizable radioactive wastes from storage facilities

    International Nuclear Information System (INIS)

    This report provides guidance for strategic planning and implementation of resuspension and retrieval of stored fluid or fluidizable radioactive wastes. The potential risks associated with preparation and realization of these processes are included in the report, and lessons learned from previous applications are highlighted. Technological procedures and equipment used in various countries for resuspension and remobilization of stored fluidizable radioactive wastes are described in the attached annexes as potential options. Waste retrieval is a maturing technology of major importance now that Member States are moving forward in the responsible management of wastes by removal to safe interim storage or disposal. Retrieval of fluidizable wastes is a four-phase operation: (1) access to the waste, (2) mobilize the waste, (3) remove the waste; and (4) transfer the waste.This report divides successful retrieval of radioactive waste into two areas. The first area applies the concept of the waste retrieval as being the final component of a systematic process of old waste management. It also encompasses characterization as it applies to waste retrieval and downstream processes, including acceptance of wastes for treatment, conditioning, storage or disposal. It should be in conformity with national policy, as well as complying with international safety standards and environmental agreements. The second area of the report focuses on implementation of waste retrieval in a wide range of scenarios and using a wide range of retrieval approaches, equipment and technologies. Technical processes are further explained as part of the experience gained in advanced countries on the subject. A set of detailed retrieval technology descriptions by country is included as Annexes to this report. Thirteen experts from seven Member States that previously implemented, or have planned for the near future, significant resuspension and remobilization operations were involved in the preparation of

  13. 3718-F Alkali Metal Treatment and Storage Facility Closure Plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-11-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. The 3718-F Alkali Metal Treatment and Storage Facility (3718-F Facility), located in the 300 Area, was used to store and treat alkali metal wastes. Therefore, it is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989) and 40 CFR 270.1. Closure also will satisfy the thermal treatment facility closure requirements of 40 CFR 265.381. This closure plan presents a description of the 3718-F Facility, the history of wastes managed, and the approach that will be followed to close the facility. Only hazardous constituents derived from 3718-F Facility operations will be addressed.

  14. 9975 Shipping Package Performance Of Alternate Materials For Long-Term Storage Application

    International Nuclear Information System (INIS)

    The Model 9975 shipping package specifies the materials of construction for its various components. With the loss of availability of material for two components (cane fiberboard overpack and Viton(regsign) GLT O-rings), alternate materials of construction were identified and approved for use for transport (softwood fiberboard and Viton(regsign) GLT-S O-rings). As these shipping packages are part of a long-term storage configuration at the Savannah River Site, additional testing is in progress to verify satisfactory long-term performance of the alternate materials under storage conditions. The test results to date can be compared to comparable results on the original materials of construction to draw preliminary conclusions on the performance of the replacement materials.

  15. Draft environmental impact statement on a proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Volume 2, Appendix F, Description and impacts of storage technology alternatives

    International Nuclear Information System (INIS)

    This appendix presents a description and evaluation of currently available spent nuclear fuel storage technologies, and their applicability to foreign research reactor spent nuclear fuel. These technologies represent the range of alternatives dW would be available to implement the proposed action. Some of these technologies are currently in use at US Department of Energy (DOE) facilities. Several dry storage cask and/or building designs have been licensed by the US Nuclear Regulatory Commission (NRC) and are operational with commercial nuclear power plant spent fuel at several locations. This appendix also discusses potential storage sites and impacts of foreign research reactor spent nuclear fuel storage at these locations

  16. The 4843 Alkali Metal Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    The 4843 AMSF has been used primarily to provide a centralized building to receive and store dangerous and mixed alkali metal waste, including sodium and lithium, which has been generated at the Fast Flux Test Facility and at various other Hanford Site operations that used alkali metals. Most of the dangerous and mixed alkali metal waste received consists of retired equipment from liquid sodium processes. The unit continues to store material. In general, only solid alkali metal waste that is water reactive is stored at the 4843 AMSF. The 4843 AMSF will be closed in a manner consistent with Ecology guidelines and regulations (WAC 173-303-610). The general closure procedure is detailed as follows

  17. Probabilistic risk analysis for Test Area North Hot Shop Storage Pool Facility

    International Nuclear Information System (INIS)

    A storage pool facility used for storing spent fuel and radioactive debris from the Three Mile Island (TMI) accident was evaluated to determine the risk associated with its normal operations. Several hazards were identified and examined to determine if any any credible accident scenarios existed. Expected annual occurrence frequencies were calculated for hazards for which accident scenarios were identified through use of fault trees modeling techniques. Fault tree models were developed for two hazards: (1) increased radiation field and (2) spread of contamination. The models incorporated facets of the operations within the facility as well as the facility itself. 6 refs

  18. Two energy storage alternatives for a solar-powered sustainable single floor desert home

    KAUST Repository

    Serag-Eldin, M. A.

    2010-09-30

    This paper is concerned with the thermodynamic analysis of a totally solarpowered desert home. The home is air-conditioned and provides all modern comforts and facilities. It features closely spaced, roof mounted photovoltaic modules, which collect the solar energy driving the whole energy system. During the day time, the modules form an elevated horizontal surface above the roof, shielding it from direct solar radiation. After sunset, the photovoltaic modules are flipped vertically upwards to expose the roof to the sky, thus enhancing night-time cooling. Two methods of energy storage are proposed and compared, one using solely battery storage of electrical output, and the other employing a combination of cold water storage and battery storage. The analysis is based on detailed dynamic heat transfer calculations for the entire building envelope, coupled with a solar radiation model, and followed by energy balances. The results reveal that indeed it is feasible to employ solar energy as the only source of energy to power the home, and that each storage system has its own merits and shortcomings. © 2010 WIT Press.

  19. 30 CFR 57.4160 - Underground electric substations and liquid storage facilities.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Underground electric substations and liquid..., DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL... Underground electric substations and liquid storage facilities. The requirements of this standard apply...

  20. Neutron spectrometry at the interim storage facility for spent nuclear fuel

    CERN Document Server

    Králik, M; Studeny, J

    2002-01-01

    Dosimetric characteristics of neutron and photon components of mixed fields around casks for spent nuclear fuel have been determined at various places at the dry interim storage facility. The results obtained with metrological grade instruments were compared with data provided by usual survey meters for both neutrons and photons.

  1. A preliminary analysis of floating production storage and offloading facilities with gas liquefaction processes

    DEFF Research Database (Denmark)

    Nguyen, Tuong-Van; Carranza-Sánchez, Yamid Alberto; Junior, Silvio de Oliveira

    2016-01-01

    Floating, production, storage and offloading (FPSO) plants are facilities used in upstream petroleum processing. They have gained interest because they are more flexible than conventional plants and can be used for producing oil and gas in deep-water fields. In general, gas export is challenging...

  2. A study on safety analysis methodology in spent fuel dry storage facility

    International Nuclear Information System (INIS)

    Collection and review of the domestic and foreign technology related to spent fuel dry storage facility. Analysis of a reference system. Establishment of a framework for criticality safety analysis. Review of accident analysis methodology. Establishment of accident scenarios. Establishment of scenario analysis methodology

  3. Norwegian work on establishing a combined storage and disposal facility for low and intermediate level waste

    International Nuclear Information System (INIS)

    The IAEA has, through its Waste Management Assessment and Technical Review Programme (WATRP), evaluated policies and facilities related to management of radioactive waste in Norway. It is concluded that the Himdalen site, in combination with the chosen engineering concept, can be suitable for the storage and disposal of the relatively small amounts of Norwegian low and intermediate level waste

  4. An improvement program of Lan-Yu radwaste receiving and storage facility in Taiwan, ROC

    International Nuclear Information System (INIS)

    Low level waste generated from three nuclear power plants in Taiwan is stored at Lan-Yu. The storage facility comprises 23 near-surface concrete trenches, inspection center, office building, etc., and is operated by the Radwaste Administration. The construction was completed in January 1982 and has been receiving waste since May 1982. Up to date, about 35,500 drums of solidified waste have been stored in this facility. An improvement program for the existing receiving and storage operation at Lan-Yu facility began in 1984 by the Radwaste Administration. The first step in this effort will be to install a semi-automatic inspection line in the inspection center and a remote-controlled unloading equipment for the storage operation. The new installation will enhance the efficiency and reduce exposure to inspectors. Detailed engineering design was already completed in January 1985. The installation will be completed in February 1987. The second step will be to develop an upgraded design for the second phase construction of the facility. The intent of this design change based on the ALARA concept is to reduce the exposure to workers and at the same time preserve the landscape. Thus, the new design will incorporate remote handling, minimizing exposure to workers and landscaping at the storage area. The concept design was completed in August 1986

  5. 30 CFR 75.1912 - Fire suppression systems for permanent underground diesel fuel storage facilities.

    Science.gov (United States)

    2010-07-01

    ... underground diesel fuel storage facilities. 75.1912 Section 75.1912 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES... suppression system shall provide automatic fire detection and automatic fire suppression for all areas...

  6. A PROBABILISTIC INVENTORY MODEL FOR CONDITIONAL CREDIT PERIOD AND LEAD TIME WITH MULTIPLE STORAGE FACILITIES

    OpenAIRE

    S S Mishra; Himanshu Pandey; Singh, R. S.

    2008-01-01

    A probabilistic inventory model for conditional credit period with exponential demand, non-zero lead time and multiple storage facility has been developed. The behaviour of total expected cost (TEC) has been examined and the use and application of the model is demonstrated with the help of a numerical example.

  7. A PROBABILISTIC INVENTORY MODEL FOR CONDITIONAL CREDIT PERIOD AND LEAD TIME WITH MULTIPLE STORAGE FACILITIES

    Directory of Open Access Journals (Sweden)

    S. S. Mishra

    2008-01-01

    Full Text Available A probabilistic inventory model for conditional credit period with exponential demand, non-zero lead time and multiple storage facility has been developed. The behaviour of total expected cost (TEC has been examined and the use and application of the model is demonstrated with the help of a numerical example.

  8. The thermal regime of underground storage facility for heat-generating radiation hazardous materials

    International Nuclear Information System (INIS)

    As a model case study the authors have chosen the theoretical development carried out by experts of the Mining Institute KSC RAS concerning design-layout of the spent nuclear fuel (SNF) underground storage facility. The object is to be modelled in the rock mass at a depth of 100 m using artificial (reinforced concrete canisters, built-in reinforced concrete constructions) and natural (rock) protection barriers. The fuel storage time is 50 years. And it is necessary to provide both reliability and lifetime of the storage facility and SNF decay-heat removal. Heat removal should be arranged in order to exclude possible overheating (source surface 358 K, granite 373) as well as to guarantee none of high temperature gradients in the protection constructions. The work is aimed at: (1) showing possibilities of thermal regime modelling for extremely important facility using COMSOL software; (2) determining degree of model thermophysical parameters impact and values of air consumption on the SNF longterm storage facility thermal regime. (orig.)

  9. A study on safety analysis methodology in spent fuel dry storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Che, M. S.; Ryu, J. H.; Kang, K. M.; Cho, N. C.; Kim, M. S. [Hanyang Univ., Seoul (Korea, Republic of)

    2004-02-15

    Collection and review of the domestic and foreign technology related to spent fuel dry storage facility. Analysis of a reference system. Establishment of a framework for criticality safety analysis. Review of accident analysis methodology. Establishment of accident scenarios. Establishment of scenario analysis methodology.

  10. Final geotechnical study, DARA Solid Storage Facility, Y-12 Bear Creek Burial Grounds, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The DARA Solid Storage Facility is located north of Gate 4 in the Y-12 Bear Creek Burial Grounds. It was constructed to temporarily store contaminated soil excavated during closure of the Oil Retention Ponds project. The ground surface around the perimeter of the building ranges from about 942 feet Mean Sea Level (MSL) to 936 feet MSL Surface drainage is away from the building, with most of the surface runoff flowing into the drainage ditch east of the building. In order for the DARA Solid Storage Facility (SSF) to be a RCRA permitted hazardous waste storage facility, you have informed us that the height of the water in the sediment cannot exceed one foot. The purposes of this study are to: Obtain subsurface data from the soil stored within the DARA Solid Storage Facility; classify the soil samples and conduct pertinent on-site laboratory tests to characterize the physical parameters of the soil; review groundwater information from nearby monitoring wells; review provided piezometer data, and integrate this with Ogden obtained data and analyze both; review other pertinent documents and drawings; comment as to why we believe that there is a reduced flow of water over time from the soil into the sumps; as appropriate, develop recommendations regarding possible methods that can be used to remove additional water from the soil; and provide other comments we believe are pertinent to a geotechnical analysis of the SSF soil-water relationship

  11. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear and Industrial Safety Agency (NISA: which prepares necessary regulations for Spent Fuel Interim Storage Facilities). In 2011 fiscal year, JNES carried out R and D for UT test of welded canister lids which is required for concrete cask storage facilities. And also, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel at cask drop accidents and PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be carried out in 2012 fiscal year and after. (author)

  12. Dry storage facility for spent fuel or high-level wastes

    International Nuclear Information System (INIS)

    The French Atomic Energy Commission (CEA) has specific irradiated fuels which, due to their properties, cannot be reprocessed directly in existing industrial facilities. Accordingly, for the spent fuels from the EL4 and OSIRIS power plants, the CEA has been faced with the problem of selecting a process that will allow the storage of these materials under satisfactory technical and economic conditions. The authors discuss how three conditions must be satisfied to store irradiated fuels releasing heat: containment of radioactive materials, biological shielding, and thermal cooling to guarantee an acceptable temperature- level throughout. In view of the need for an interim storage facility using a simple cooling process requiring only minimal maintenance and monitoring, dry storage in a concrete vault cooled by natural convection was selected. This choice was made within the framework of a research and development program in which theoretical heat transfer investigations and mock-up tests confirmed the feasibility of cooling by natural convection

  13. Development of technical design for waste processing and storage facilities for Novi Han repository

    International Nuclear Information System (INIS)

    Empresarion Agrupados Internacional S.A. (Spain) and ENPRO Consult Ltd. (Bulgaria) were awarded a contract by the Central Finance and Contracts Unit to develop the technical design of the waste processing and storage facilities at the Novi Han repository. At present conceptual design phase is finished. This conceptual design covers the definition of the basic design requirements to be applied to the installations defined above, following both European and Bulgarian legislation. In this paper the following items are considered: 1) Basic criteria for the layout and sizing of buildings; 2) Processing of radioactive waste, including: treatment and conditioning of disused sealed sources; treatment of liquid radioactive wastes; treatment of solid radioactive waste; conditioning of liquid and solid radioactive waste; 3) Control of waste packages and 4) Storage of radioactive waste, including storage facility and waste packages. An analysis of inventories of stored and estimated future wastes and its subsequent processes is also presented and the waste streams are illustrated

  14. Structural and seismic analyses of waste facility reinforced concrete storage vaults

    International Nuclear Information System (INIS)

    Facility 317 of Argonne National Laboratory consists of several reinforced concrete waste storage vaults designed and constructed in the late 1940's through the early 1960's. In this paper, structural analyses of these concrete vaults subjected to various natural hazards are described, emphasizing the northwest shallow vault. The natural phenomenon hazards considered include both earthquakes and tornados. Because these vaults are deeply embedded in the soil, the SASSI (System Analysis of Soil-Structure Interaction) code was utilized for the seismic calculations. The ultimate strength method was used to analyze the reinforced concrete structures. In all studies, moment and shear strengths at critical locations of the storage vaults were evaluated. Results of the structural analyses show that almost all the waste storage vaults meet the code requirements according to ACI 349--85. These vaults also satisfy the performance goal such that confinement of hazardous materials is maintained and functioning of the facility is not interrupted

  15. Development of a variable climate controlled portable storage facility

    Science.gov (United States)

    Timmins, Mitchel; Yadav, Kamal; Iroanusi, Kennedy; Tickle, Andrew J.

    2012-10-01

    This paper focuses on the development of a portable variable climate controlled system that can be tailored to the requirements of the item to be stored by manipulating the temperature, humidity and light levels within the controlled area. This could be used to store anything from bio-chemical samples (to preserve them from field work) to cooled electronics (prior to deployment in a given situation) to foodstuffs (such as wine and other alcohols). In this situation however, to provide a relatively simplistic example, the environment will be used to store wine. The system is adaptive in that anything can be stored within it, assuming the storage parameters are known in order to correctly configure the environment. In this paper a microcontroller (PICF4520) is connected to a fridge with various sensors attached to monitor and manipulate the environment and adjust it accordingly. For the chosen item to be stored, a temperature of 13- 14oC is required, a high humidity level and a non-Ultraviolent (UV) light source. This work thus allows for a small handheld unit that could be used to control the climate within without the need for the traditional 12 - 16 foot size portable units traditionally used. The unit could be left in the field and run off a solar cell to assist in longer term studies. This paper presents how the microcontroller is connected to the fridge and its sensors, how it manipulates the environment and the process by which the temperature and other factors can be changed without having to edit and recompile the C code, this allows for a much more friendly device interface.

  16. Issues at Stake When Considering Long Term Storage of HLW a Comprehensive Approach to Designing the Facility

    International Nuclear Information System (INIS)

    CEA has been conducting a comprehensive R and D program to identify and study key HLW storage design criteria to possibly meet the lifetime goal of a century and beyond. A novel approach is being used since such installations must be understood as a global system comprised of various materials and hardware components, canisters, concrete and steel structures and specific procedures covering engineering steps from construction to operation including monitoring, care and maintenance as well as licensing. The challenge set by such a lifetime design goal made the R and D people focus on issues at stake and relevant to long term HLW storage in particular heat management, the effect of time on materials and the sustainability of care and maintenance. This opened up the R and D field from fundamental research areas to more conventional and technical aspects. Two major guiding principles have been devised as key design goals for the storage concepts under consideration. One is the paramount function of retrievability, which must allow the safe retrieval of any HLW package from the facility at any given time. Next is the passive containment philosophy requiring that a dual-barrier system be considered. In the case of spent fuel, CEA's early assessment of the long-term behavior of cladding shows that it may not qualify as a reliable barrier over a long period of time. Therefore, the overriding strategy of preventing corrosion and material degradation to achieve canister protection, and therefore containment of radioactive material throughout the time of period envisaged, is at the heart of the R and D program and several design alternatives are being studied to meet that objective. For instance available thermal power from SF is used to establish dry corrosion conditions within the storage facility. The paper reviews all of these different R and D and engineering aspects

  17. Issues at stake when considering long term storage of HLW. A comprehensive approach to designing the facility

    International Nuclear Information System (INIS)

    CEA has been conducting a comprehensive R and D program to identify and study key HLW storage design criteria to possibly meet the lifetime goal of a century and beyond. A novel approach is being used since such installations must be understood as a global system comprised of various materials and hardware components, canisters, concrete and steel structures and specific procedures covering engineering steps from construction to operation including monitoring, care and maintenance as well as licensing. The challenge set by such a lifetime design goal made the R and D people focus on issues at stake and relevant to long term HLW storage in particular heat management, the effect of time on materials and the sustainability of care and maintenance. This opened up the R and D field from fundamental research areas to more conventional and technical aspects. Two major guiding principles have been devised as key design goals for the storage concepts under consideration. One is the paramount function of retrievability, which must allow the safe retrieval of any HLW package from the facility at any given time. Next is the passive containment philosophy requiring that a two-barrier system be considered. In the case of spent fuel, CEA's early assessment of the long-term behaviour of cladding shows that it cannot qualify as a reliable barrier over a long period of time. Therefore, the overriding strategy of preventing corrosion and material degradation to achieve canister protection, and therefore containment of radioactive material throughout the time of period envisaged, is at the heart of the R and D program and several design alternatives are being studied to meet that objective. For instance available thermal power from SF is used to establish dry corrosion conditions within the storage facility. The paper reviews all of these different R and D and engineering aspects. (author)

  18. Return of isotope capsules to the Waste Encapsulation and Storage Facility

    International Nuclear Information System (INIS)

    Cesium-137 and strontium-90 isotopes were removed from Hanford Site high-level tank wastes, and were encapsulated at the Hanford Site's Waste Encapsulation and Storage Facility (WESF), beginning in 1974. Over the past several years, radioactive isotope capsules have been sent to other U.S. Department of Energy (DOE)-controlled sites to be used for research and development applications, as well as leased to a number of commercial facilities for commercial applications (e.g., sterilization of medical supplies). Due to uncertainty regarding the cause of the release of a small quantity of cesium-137 to an isolated water basin from a WESF cesium-137 capsule in a commercial facility in Decatur, Georgia, the DOE has determined that it needs to return leased capsules from IOTECH, Incorporated (IOTECH), Northglenn, Colorado; Pacific Northwest Laboratory (PNL), Richland, Washington; and the Applied Radiant Energy Corporation (ARECO), Lynchburg, Virginia; to the WESF Facility on the Hanford Site, to ensure safe management and storage, pending final disposition. All of these capsules located at the commercial facilities were successfully tested during Calendar Year 1993, and none showed any indication of off-normal specifications. Storage at the WESF will continue under the actions selected in the Record of Decision for the Final Environmental Impact Statement: Disposal of Hanford Defense High-Level, Transuranic and Tank Wastes, Hanford Site, Richland, Washington

  19. Modification and expansion of X-7725A Waste Accountability Facility for storage of polychlorinated biphenyl wastes at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) must manage wastes containing polychlorinated biphenyls (PCBs) in accordance with Toxic Substances Control Act (TSCA) requirements and as prescribed in a Federal Facilities Compliance Agreement (FFCA) between DOE and the U.S. Environmental Protection Agency (EPA). PCB-containing wastes are currently stored in the PORTS process buildings where they are generated. DOE proposes to modify and expand the Waste Accountability facility (X-7725A) at the Portsmouth Gaseous Diffusion Plant (PORTS), Piketon, Ohio, to provide a central storage location for these wastes. The proposed action is needed to eliminate the fire and safety hazards presented by the wastes. In this EA, DOE considers four alternatives: (1) no action, which requires storing wastes in limited storage areas in existing facilities; (2) modifying and expanding the X-7725A waste accountability facility; (3) constructing a new PCB waste storage building; and (4) shipping PCB wastes to the K-25 TSCA incinerator. If no action is taken, PCB-contaminated would continue to be stored in Bldgs X-326, X-330, and X-333. As TSCA cleanup activities continue, the quantity of stored waste would increase, which would subsequently cause congestion in the three process buildings and increase fire and safety hazards. The preferred alternative is to modify and expand Bldg. X-7725A to store wastes generated by TSCA compliance activities. Construction, which could begin as early as April 1996, would last approximately five to seven months, with a total peak work force of 70

  20. Modification and expansion of X-7725A Waste Accountability Facility for storage of polychlorinated biphenyl wastes at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The US Department of Energy (DOE) must manage wastes containing polychlorinated biphenyls (PCBs) in accordance with Toxic Substances Control Act (TSCA) requirements and as prescribed in a Federal Facilities Compliance Agreement (FFCA) between DOE and the U.S. Environmental Protection Agency (EPA). PCB-containing wastes are currently stored in the PORTS process buildings where they are generated. DOE proposes to modify and expand the Waste Accountability facility (X-7725A) at the Portsmouth Gaseous Diffusion Plant (PORTS), Piketon, Ohio, to provide a central storage location for these wastes. The proposed action is needed to eliminate the fire and safety hazards presented by the wastes. In this EA, DOE considers four alternatives: (1) no action, which requires storing wastes in limited storage areas in existing facilities; (2) modifying and expanding the X-7725A waste accountability facility; (3) constructing a new PCB waste storage building; and (4) shipping PCB wastes to the K-25 TSCA incinerator. If no action is taken, PCB-contaminated would continue to be stored in Bldgs X-326, X-330, and X-333. As TSCA cleanup activities continue, the quantity of stored waste would increase, which would subsequently cause congestion in the three process buildings and increase fire and safety hazards. The preferred alternative is to modify and expand Bldg. X-7725A to store wastes generated by TSCA compliance activities. Construction, which could begin as early as April 1996, would last approximately five to seven months, with a total peak work force of 70.

  1. Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

    International Nuclear Information System (INIS)

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses

  2. Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

  3. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  4. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    International Nuclear Information System (INIS)

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system

  5. Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

    International Nuclear Information System (INIS)

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL's weapons research, development, and testing (WRD ampersand T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL's inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information

  6. Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

  7. 36 CFR 1232.12 - Under what conditions may Federal records be stored in records storage facilities?

    Science.gov (United States)

    2010-07-01

    ... meets the provisions of 36 CFR part 1234. (b) Unscheduled records (1) Any storage facility that meets the provisions of 36 CFR part 1234. (2) Also requires prior notification to NARA (see § 1232.14(b... provisions of 36 CFR part 1234. (d) Vital records Storage facility must meet the provisions of 36 CFR...

  8. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, W.W.

    1997-12-30

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

  9. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    International Nuclear Information System (INIS)

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

  10. Disposal facility in olkiluoto, description of above ground facilities in lift transport alternative

    International Nuclear Information System (INIS)

    The above ground facilities of the disposal plant on the Olkiluoto site are described in this report as they will be when the operation of the disposal facility starts in the year 2020. The disposal plant is visualised on the Olkiluoto site. Parallel construction of the deposition tunnels and disposal of the spent fuel canisters constitute the principal design basis of the disposal plant. The annual production of disposal canisters for spent fuel amounts to about 40. Production of 100 disposal canisters has been used as the capacity basis. Fuel from the Olkiluoto plant and from the Loviisa plant will be encapsulated in the same production line. The disposal plant will require an area of about 15 to 20 hectares above ground level. The total building volume of the above ground facilities is about 75000 m3. The purpose of the report is to provide the base for detailed design of the encapsulation plant and the repository spaces, as well as for coordination between the disposal plant and ONKALO. The dimensioning bases for the disposal plant are shown in the Tables at the end of the report. The report can also be used as a basis for comparison in deciding whether the fuel canisters are transported to the repository by a lift or by a vehicle along the access tunnel. (orig.)

  11. Regulatory aspects of construction of dry spent nuclear fuel storage facility in Russia

    International Nuclear Information System (INIS)

    Full text: Construction of the first spent fuel (SF) dry storage facility (XOT-2) in Russia began in 2004 on a site at 'The Mining and Chemical Enterprise'(MCE). This storage facility is supposed to be used for temporary storage of SF from VVER-1000 and RBMK-1000 reactors. The whole projected capacity of the storage facility is more than 33000 tons of uranium. Systems for SF storage have two physical barriers: hermetic capsules and hermetic storage 'sockets'. It is necessary to guarantee the following requirements for SF storage: storage duration is not less than 50 years, storage medium is nitrogen, storage temperature is from 300 deg. C to 350 deg. C, water content is less than 25 g/cm3. In accordance with regulations (Article 26 of the Federal Law 'On the Use of Nuclear Energy'), no activity in the field of nuclear energy use is allowed without a licence for its execution. The Law defines several categories of facilities including the category 'storage of SF' The list of types of activities in the field of nuclear energy use that require licensing is established by the Government of the Russian Federation in the 'Provisions on licensing of activity in the field of nuclear energy use'. The Provisions include such types of activities as siting, construction, operation and decommissioning of SF storage. To obtain a licence, an applicant submits a set of documents to Rostechnadzor. The most important part of the licensing procedure is expert review of the documents justifying the safety of the planned facility. The purpose of this review is to give an independent assessment about the safety of the type of activity proposed by the licence applicant, to assess proposed technical solutions related to safety assurance. The results of the assessment are then set forth in a technical document prepared by the Safety and Engineering Centre for nuclear and Radiation Safety (SEC NRC). The review of the complete set of documents justifying the safety of XOT-2 construction was

  12. Loads imposed on dual purpose casks in German on-site-storage facilities for long term intermediate storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    In accordance with recent changes of the atomic energy act and in order to secure reliable removal of spent fuel from the nuclear power plants' fuel storage ponds the German utilities filed license applications for a total of 12 onsite- storage facilities for spent fuel assemblies. By the end of 2003 the last of these storage facilities were licensed and are currently under construction. The first on-site-storage facility of that line became operational in late 2002. There are several design lines of storage facilities with different handling procedures or possible accident conditions. Short term interim storage facilities for a few casks are characterized by individual concrete hoods shielding the casks in horizontal position whereas long term intermediate storage facilities currently erected for large numbers of casks typically feature a condensed pattern of casks stored in upright position and massive structures of reinforced concrete. TUeV Hannover/Sachsen-Anhalt e. V. (now TUeV NORD EnSys Hannover GmbH and Co. KG) has been contracted as a body of independent experts for the assessment of all related safety requirements on behalf of the national licensing authority, the federal office for radiation protection (BfS)

  13. Technical, economic and institutional aspects of regional spent fuel storage facilities

    International Nuclear Information System (INIS)

    A particular challenge facing countries with small nuclear programmes is the preparation for extended interim storage and then disposal of their spent nuclear fuel. The costs and complications of providing for away-from-reactor storage facilities and/or geological repositories for relatively small amounts of spent fuel may be prohibitively high, motivating interest in regional solutions. This publication addresses the technical, economic and institutional aspects of regional spent fuel storage facilities (RSFSF) and is based on the results of a series of meetings on this topic with participants from IAEA Member States. Topics discussed include safety criteria and standards, safeguards and physical protection, fuel acceptance criteria, long term stability of systems and stored fuel, selection of site, infrastructure aspects, storage technology, licensing, operations, transport, decommissioning, as well as research and development. Furthermore the publication comprises economic, financial and institutional considerations including organizations and legal aspects followed by political and public acceptance and ethical considerations. Approaches and processes for implementation are discussed, as well as the overall benefits and risks of implementing a regional facility. It is illustrated that implementing a RSFSF facility would involve simultaneously addressing a wide range of diverse challenges. The appendix to this report tabulates the numerous issues that have been touched upon in the study. It appears, however, from the discussions that the challenges can in principle be met; the RSFSF concept is technically feasible and potentially economically viable. The technical committees producing this report did not identify any obvious institutional deficiencies that would prevent completion of such a project. Storing spent fuel in a few safe, reliable, secure facilities could enhance safeguards, physical protection and non-proliferation benefits. The committee also

  14. Materials and degradation modes in an alternative LLW [low-level waste] disposal facility

    International Nuclear Information System (INIS)

    The materials used in the construction of alternative low-level waste disposal facilities will be subject to interaction with both the internal and the external environments associated with the facilities and unless precautions are taken, may degrade, leading to structural failure. This paper reviews the characteristics of both environments with respect to three alternative disposal concepts, then assesses how reaction with them might affect the properties of the materials, which include concrete, steel-reinforced concrete, structural steel, and various protective coatings and membranes. It identifies and evaluates the probability of reactions occurring which might lead to degradation of the materials and so compromise the structure. The probability of failure (interpreted relative to the ability of the structure to restrict ingress and egress of water) is assessed for each material and precautionary measures, intended to maximize the durability of the facility, are reviewed. 19 refs., 2 tabs

  15. Central Storage Facility Project In Colombia To Provide The Safe Storage And Protection Of High-Activity Radioactive Sources

    International Nuclear Information System (INIS)

    The Global Threat Reduction Initiative (GTRI) reduces and protects vulnerable nuclear and radiological material located at civilian sites worldwide. Internationally, over 40 countries are cooperating with GTRI to enhance the security of these materials. The GTRI program has worked successfully with foreign countries to remove and protect nuclear and radioactive materials, including orphaned and disused high-activity sources. GTRI began cooperation with the Republic of Colombia in April 2004. This cooperation has been a resounding success by securing forty high-risk sites, consolidating disused/orphan sources at an interim secure national storage facility, and developing a comprehensive approach to security, training, and sustainability. In 2005 the Colombian Ministry of Mines and Energy requested the Department of Energy's support in the construction of a new Central Storage Facility (CSF). In December 2005, the Ministry selected to construct this facility at the Institute of Geology and Mining (Ingeominas) site in Bogota. This site already served as Colombia's national repository, where disused sources were housed in various buildings around the complex. The CSF project was placed under contract in May 2006, but environmental issues and public protests, which led to a class action lawsuit against the Colombian Government, forced the Ministry to quickly suspend activities, thereby placing the project in jeopardy. Despite these challenges, however, the Ministry of Mines and Energy worked closely with public and environmental authorities to resolve these issues, and continued to be a strong advocate of the GTRI program. In June 2008, the Ministry of Mines and Energy was granted the construction and environmental licenses. As a result, construction immediately resumed and the CSF was completed by December 2008. A commissioning ceremony was held for the new facility in January 2009, which was attended by representatives from the Department of Energy, U.S. Embassy, and

  16. The regulatory approach for spent nuclear storage and conditioning facility: The Hanford example

    International Nuclear Information System (INIS)

    Hearings held before the House Subcommittee on Energy and Mineral Resources in March 1994, requested that officials of federal agencies and other experts explore options for providing regulatory oversight of the US Department of Energy (DOE) facilities and operations. On January, 25, 1995, the DOE, supported by the White House Office of Environmental Quality and the Office of Management and Budget, formally initiated an Advisory Committee on External Regulation of DOE Nuclear Safety. In concert with this initiative and public opinion, the DOE Richland Operations Office has initiated the K Basin Spent Nuclear Fuel Project -- Regulatory Policy. The DOE has established a program to move the spent nuclear fuel presently stored in the K Basins to a new storage facility located in the 200 East Area of the Hanford Site. New facilities will be designed and constructed for safe conditioning and interim storage of the fuel. In implementing this Policy, DOE endeavors to achieve in these new facilities ''nuclear safety equivalency'' to comparable US Nuclear Regulatory Commission (NRC)-licensed facilities. The DOE has established this Policy to take a proactive approach to better align its facilities to the requirements of the NRC, anticipating the future possibility of external regulation. The Policy, supplemented by other DOE rules and directives, form the foundation of an enhanced regulatory, program that will be implemented through the DOE K Basin Spent Nuclear Fuel Project (the Project)

  17. Safe and durable storage of waste from reprocessing in E-EV-SE and ECC facilities

    International Nuclear Information System (INIS)

    The main industrial facilities involved in closing the back-end of the nuclear fuel cycle in France are La Hague reprocessing plant, in which fission products and minor actinides are vitrified and recyclable materials (U, Pu) are recovered and purified, and the MELOX plant where the recovered plutonium is used to fabricate MOX fuel. These facilities are operated by the COGEMA/AREVA Group. With a reprocessing capacity of 1,700 tHM/year, the La Hague site accounts for some two-thirds of the commercial capacity offered worldwide (LWR fuel), while MELOX plant produces 145 tHM of MOX per year. COGEMA commitment to sustainable development is at the core of its industrial strategy, through permanent care about minimizing releases to environment while reducing the amount of unavoidably generated waste to be disposed of. The final disposal of waste, and in particular regarding waste not compatible with surface repository, has become one of the key issues of the nuclear industry from both technological and economical aspects, not to mention the public acceptance aspects. Final disposal being under investigation, wastes not compatible with surface disposal are today temporary stored in interim storage facilities. Reprocessing coupled with interim storage, and if required long term interim storage thus provide duration flexibility to set up final disposal. The paper presents: a description of COGEMA interim storage facilities; an investigation regarding the possible lifetime extension of interim storage facilities; an assessment of the ability of the storage to cope with secular operation. In conclusion, through its nuclear fuel cycle activities, particularly in the fields of reprocessing and recycling, COGEMA has been accumulating knowledge and know-how to design and build safe and durable interim storage facilities. A significant optimization has been conducted from both technical and economical aspects, to customize the storage to the characteristics of the waste to be

  18. Concepts for pumped hydro storage facilities in former opencast mining facilities

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, Detlef; Jordan, Michael [Helmut-Schmidt-Univ. Hamburg (Germany). Electrical Power Systems

    2010-07-01

    Storage of high energy amounts as needed in the electrical power system is limited to only some technologies. One of these, the pumped storage hydro power plants (PSHPP), requires special geological conditions and a costly permission procedure for conventional installations. Also the influence of PSHPP on the environment during the building phase and later in operation is a point of strong discussion. This paper proposes the installation of new PSHPP in opencast mining areas, which remain from coal mining or similar processes. Therefore the idea and the technical application of the proposed technology are introduced. The realization of the concept can bring big advantages compared to a conventional installation. Technical, organizational and financial advantages are explained in detail. (orig.)

  19. Release of radionuclides following severe accident in interim storage facility. Source term determination

    International Nuclear Information System (INIS)

    Among the severe accidents that can cause the release of radionuclides from an interim storage facility, with a consequent relevant radiological impact on the population, there is the impact of an aircraft on the facility. In this work, a safety assessment analysis for the case of an aircraft crash into an interim storage facility is tackled. To this aim a methodology, based upon DOE, IAEA and NUREG standard procedures and upon conservative yet realistic hypothesis, has been developed in order to evaluate the total radioactivity, source term, released to the biosphere in consequence of the impact, without recurring to the use of complicated numerical codes. The procedure consists in the identification of the accidental scenarios, in the evaluation of the consequent damage to the building structures and to the waste packages and in the determination of the total release of radionuclides through the building-atmosphere interface. The methodology here developed has been applied to the case of an aircraft crash into an interim storage facility currently under design. Results show that in case of perforation followed by a fire incident the total released activity would be greater of some orders of magnitude with respect to the case of mere perforation. (author)

  20. Criticality safety evaluation report for spent nuclear fuelprocessing and storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    Schwinkendorf, K.N., Fluor Daniel Hanford

    1997-03-24

    This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially- built baskets containing either 54 Mark IV or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the MCO/Cask, operations at the Cold Vacuum Drying Facility (CVDF), and storage in the Canister Storage Building (CSB). Many conservatisms have been built into this analysis, the primary one being the selection of the k{sub eff} @ 0.95 criticality safety limit.

  1. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

  2. Pilot scale facility to determine gaseous emissions from livestock slurry during storage

    DEFF Research Database (Denmark)

    Petersen, Søren O; Skov, Morten; Drøscher, Per;

    2009-01-01

    Livestock production is a growing source of air pollution, locally and to the wider environment. Improved livestock manure management has the potential to reduce environmental impacts, but there is a need for methodologies to precisely quantify emissions. This paper describes and evaluates a novel...... storage facility for livestock slurry consisting of eight 6.5-m3 cylindrical units. The stores may be equipped with airtight covers and ventilated during storage or during measurement only. Each store has eight air inlets (160 mm diameter) and a single outlet in the cover connected to a main ventilation...

  3. Audits of hazardous waste TSDFs let generators sleep easy. [Hazardous waste treatment, storage and disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Carr, F.H.

    1990-02-01

    Because of the increasingly strict enforcement of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA), generators of hazardous waste are compelled to investigate the hazardous waste treatment, storage and disposal facility (TSDF) they use. This investigation must include an environmental and a financial audit. Simple audits may be performed by the hazardous waste generator, while more thorough ones such as those performed for groups of generators are more likely to be conducted by environmental consultants familiar with treatment, storage, and disposal techniques and the regulatory framework that guides them.

  4. Waste and Encapsulation Storage Facility (WESF) Essential and Support Drawing List

    International Nuclear Information System (INIS)

    The drawings identified in this document will comprise the Waste Encapsulation and Storage Facility essential and support drawing list. This list will replace drawings identified as the ''WESF Essential and support drawing list''. Additionally, this document will follow the applicable requirements of HNF-PRO-242 ''Engineering Drawing Requirements'' and FSP-WESF-001, Section EN-1 ''Documenting Engineering Changes''. An essential drawing is defined as an engineering drawing identified by the facility staff as necessary to directly support the safe operation or maintenance of the facility. A support drawing is defined as a drawing identified by the facility staff that further describes the design details of structures, systems, or components shown on essential drawings or is frequently used by the support staff

  5. Interface Issues Arising Between Storage and Transport for Storage Facilities Using Storage/Transport Dual Purpose Dry Metal Casks

    International Nuclear Information System (INIS)

    The dual purpose dry metal casks were developed as a low cost and reliable design to handle spent fuel safely, not only in relation to storage, but also transportation. One of its main advantages is to enhance worker protection against radiation while reducing possible direct manipulation of the spent fuel. In order to define regulation and the use of this type of casks, a traditional approach can be used, based on the study of every individual aspect. However a new type of approach is possible, called the “holistic approach”, taking into account the different aspects as a whole. (author)

  6. Evaluation of alternatives to fungicide to control postharvest gray mold alone or with ozone storage in grapes, 2011

    Science.gov (United States)

    Gray mold, caused by B. cinerea, causes severe losses since it spreads easily among berries during cold storage. Currently, it is controlled by fumigation with SO2 or SO2 emitting sheets within boxes. Alternative methods, such as storage in ozone atmospheres, are needed because SO2 is banned in orga...

  7. High Purity Germanium Gamma-PHA Assay of Uranium Storage Pigs for 321-M Facility

    Energy Technology Data Exchange (ETDEWEB)

    Dewberry, R.A.

    2001-09-18

    The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The facility also includes the 324-M storage building and the passageway connecting it to 321-M. The results of the holdup assays are essential for determining compliance with the Solid Waste's Waste Acceptance Criteria, Material Control and Accountability, and to meet criticality safety controls. This report describes and documents the use of a portable HPGe detector and EG and G Dart system that contains a high voltage power supply, signal processing electronics, a personal computer with Gamma-Vision software, and space to store and manipulate multiple 4096-channel g-ray spectra to assay for 235U content in 268 uranium shipping and storage pigs. This report includes a description of three efficiency calibration configurations and also the results of the assay. A description of the quality control checks is included as well.

  8. High Purity Germanium Gamma-PHA Assay of Uranium Storage Pigs for 321-M Facility

    International Nuclear Information System (INIS)

    The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The facility also includes the 324-M storage building and the passageway connecting it to 321-M. The results of the holdup assays are essential for determining compliance with the Solid Waste's Waste Acceptance Criteria, Material Control and Accountability, and to meet criticality safety controls. This report describes and documents the use of a portable HPGe detector and EG and G Dart system that contains a high voltage power supply, signal processing electronics, a personal computer with Gamma-Vision software, and space to store and manipulate multiple 4096-channel g-ray spectra to assay for 235U content in 268 uranium shipping and storage pigs. This report includes a description of three efficiency calibration configurations and also the results of the assay. A description of the quality control checks is included as well

  9. Alternative energy facility siting policies for urban coastal areas: executive summary of findings and policy recommendations

    Energy Technology Data Exchange (ETDEWEB)

    Morell, D; Singer, G

    1980-11-01

    An analysis was made of siting issues in the coastal zone, one of the nation's most critical natural resource areas and one which is often the target for energy development proposals. The analysis addressed the changing perceptions of citizens toward energy development in the coastal zone, emphasizing urban communities where access to the waterfront and revitalization of waterfront property are of interest to the citizen. The findings of this analysis are based on an examination of energy development along New Jersey's urban waterfront and along the Texas-Louisiana Gulf Coast, and on redevelopment efforts in Seattle, San Francisco, Boston, and elsewhere. The case studies demonstrate the significance of local attitudes and regional cooperation in the siting process. In highly urbanized areas, air quality has become a predominant concern among citizen groups and an influential factor in development of alternative energy facility siting strategies, such as consideration of inland siting connected by pipeline to a smaller coastal facility. The study addresses the economic impact of the permitting process on the desirability of energy facility investments, and the possible effects of the location selected for the facility on the permitting process and investment economics. The economic analysis demonstrates the importance of viewing energy facility investments in a broad perspective that includes the positive or negative impacts of various alternative siting patterns on the permitting process. Conclusions drawn from the studies regarding Federal, state, local, and corporate politics; regulatory, permitting, licensing, environmental assessment, and site selection are summarized. (MCW)

  10. 616 Nonradioactive Dangerous Waste Storage Facility -- Essential/support drawing list. Revision 2

    International Nuclear Information System (INIS)

    This document identifies the essential and supporting engineering drawings for the 616 Nonradioactive Dangerous Waste Storage Facility. The purpose of the documents is to describe the criteria used to identify and the plan for updating and maintaining their accuracy. Drawings are designated as essential if they relate to safety systems, environmental monitoring systems, effluents, and facility HVAC, electrical, and plumbing systems. Support drawings are those which are frequently used or describe a greater level of detail for equipment, components, or systems shown on essential drawings. A listing of drawings identified as essential or support is provided in Table A

  11. Emergency preparedness hazards assessment for the Concentrate, Storage and Transfer Facility

    International Nuclear Information System (INIS)

    This report documents this facility Emergency Preparedness Hazards Assessment (EPHA) for the Concentrate, Storage and Transfer Facility (CSTF) located on the Department of Energy (DOE) Savannah River Site (SRS). The CSTF encompasses the F-Area and the H-Area Tank Farms including the Replacement High Level Waste Evaporator (RHLWE) (3H evaporator) as a segment of the H-Area Tank Farm. This EPHA is intended to identify and analyze those hazards that are significant enough to warrant consideration in the tank farm operational emergency management programs

  12. Storage for the Fast Flux Test Facility unirradiated fuel in the Plutonium Finishing Plant Complex, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    This Environmental Assessment evaluates the proposed action to relocate and store unirradiated Fast Flux Test Facility fuel in the Plutonium Finishing Plant Complex on the Hanford Site, Richland, Washington. The US Department of Energy has decided to cease fuel fabrication activities in the 308 Building in the 300 Area. This decision was based on a safety concern over the ability of the fuel fabrication portion of the 308 Building to withstand a seismic event. The proposed action to relocate and store the fuel is based on the savings that could be realized by consolidating security costs associated with storage of the fuel. While the 308 Building belowgrade fuel storage areas are not at jeopardy by a seismic event, the US Department of Energy is proposing to cease storage operations along with the related fabrication operations. The US Department of Energy proposes to remove the unirradiated fuel pins and fuel assemblies from the 308 Building and store them in Room 192A, within the 234-5Z Building, a part of the Plutonium Finishing Plant Complex, located in the 200 West Area. Minor modifications to Room 192A would be required to accommodate placement of the fuel. The US Department of Energy estimates that removing all of the fuel from the 308 Building would save $6.5 million annually in security expenditures for the Fast Flux Test Facility. Environmental impacts of construction, relocation, and operation of the proposed action and alternatives were evaluated. This evaluation concluded that the proposed action would have no significant impacts on the human environment

  13. Computerization of nuclear material accounting and control at storage facilities of RT-1 plant, PA Mayak

    International Nuclear Information System (INIS)

    Computerized system for nuclear material (NM) accounting and control at RT-1 plant is being created on the basis of advanced engineering and programming tools, which give a possibility to ensure prompt access to the information required, to unify the accounting and report documentation, make statistical processing of the data, and trace the NM transfers in the chain of its storage at facilities of RT-1 plant. Currently, the accounting is performed in parallel, both by the old methods and with computerized system. The following functions are performed by the system at the current stage: input of data on the end product's (plutonium dioxide) quantitative and qualitative composition; data input on the localization of containers with finished products at storage facilities of the plant and the product's temporary characteristics; selective verification of the data on containers and batches, according to the criteria prespecified by the user; data protection against unauthorized access; data archiving; report documents formation and providing

  14. TSD-DOSE: A radiological dose assessment model for treatment, storage, and disposal facilities

    International Nuclear Information System (INIS)

    Past practices at US Department of Energy (DOE) field facilities resulted in the presence of trace amounts of radioactive materials in some hazardous chemical wastes shipped from these facilities. In May 1991, the DOE Office of Waste Operations issued a nationwide moratorium on shipping all hazardous waste until procedures could be established to ensure that only nonradioactive hazardous waste would be shipped from DOE facilities to commercial treatment, storage, and disposal (TSD) facilities. To aid in assessing the potential impacts of shipments of mixed radioactive and chemically hazardous wastes, a radiological assessment computer model (or code) was developed on the basis of detailed assessments of potential radiological exposures and doses for eight commercial hazardous waste TSD facilities. The model, called TSD-DOSE, is designed to incorporate waste-specific and site-specific data to estimate potential radiological doses to on-site workers and the off-site public from waste-handling operations at a TSD facility. The code is intended to provide both DOE and commercial TSD facilities with a rapid and cost-effective method for assessing potential human radiation exposures from the processing of chemical wastes contaminated with trace amounts of radionuclides

  15. An alternative format for Category I fuel cycle facility physical protection plans

    International Nuclear Information System (INIS)

    This document provides an alternative format for physical protection plans designed to meet the requirements of Title 10 of the Code of Federal Regulations, Sections 73.20, 73.45, and 73.46. These requirements apply to licensees who operate Category I fuel cycle facilities. Such licensees are authorized to use or possess a formula quantity of strategic special nuclear material. The format described is an alternative to that found under Regulatory Guide 5.52, Rev. 2 ''Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power Plants).''

  16. Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, B.S., Westinghouse Hanford

    1996-07-29

    This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

  17. European concepts for shared storage and disposal facilities for radioactive wastes?

    International Nuclear Information System (INIS)

    Geological disposal is an essential component of the long-term management of spent fuel and high-level radioactive waste. Implementation of a suitable deep repository may, however, be difficult or impossible in some (especially small) countries because of challenging geological conditions or restricted siting options, or because of the high costs involved. For these countries, shared regional or international storage and disposal facilities are a necessity. The European Parliament and the EC have both expressed support for concepts that could lead to regional shared facilities being implemented in the EU. The EC, therefore, funded two projects that form the first two steps of a staged process towards the implementation of shared regional or international storage and disposal facilities. In the period 2003 to 2005, the EC funded SAPIERR I, a project devoted to pilot studies on the feasibility of shared regional storage facilities and geological repositories, for use by European countries. The studies showed that shared regional repositories are feasible, but also that, if they are to be implemented, even some decades ahead, efforts must already be increased now. The first step would be to establish a structured framework for the work on regional repositories. This is the goal of SAPIERR II (2006-2008): to develop possible practical implementation strategies and organisational structures. These will enable a formalised, structured European Development Organisation (EDO) to be established in 2008 or afterwards for working on shared EU radioactive waste storage and disposal activities. The EDO can work in parallel with national waste programmes. Participating EU Member States will be able to use the structures developed as, when and if needed for the furtherance of their individual national policies. (authors)

  18. Characterization and reclamation assessment for the central shops diesel storage facility at Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Fliermans, C.B.; Hazen, T.C.; Bledsoe, H.W.

    1994-12-31

    The contamination of subsurface terrestrial environments by organic contaminants is a global phenomenon. The remediation of such environments requires innovative assessment techniques and strategies for successful cleanups. Using innovative approaches, the central Shops Diesel Storage Facility at the Savannah River Site (SRS) was characterized to determine the extent of subsurface diesel fuel contamination. Effective bioremediation techniques for cleaning up of the contaminant plume were established.

  19. A Facile Route to Metal Oxides/Single-Walled Carbon Nanotube Macrofilm Nanocomposites for Energy Storage

    OpenAIRE

    Cao, Zeyuan; Wei, Bingqing

    2015-01-01

    Nanocomposites consisting of transition-metal oxides and carbon nanomaterials with a desired size and structure are highly demanded for high-performance energy storage devices. Here, a facile two-step and cost-efficient approach relying on directly thermal treatment of chemical vapor deposition products is developed as a general synthetic method to prepare a family of metal oxides [MxOy (M = Fe, Co, Ni)]/single-walled carbon nanotube (SWNT) macrofilm nanocomposites. The MxOy nanoparticles obt...

  20. Safety analysis report for packaging (onsite) for the Waste Encapsulation and Storage Facility ion exchange module

    International Nuclear Information System (INIS)

    The Waste Encapsulation and Storage Facility (WESF) is in need of providing an emergency ion exchange system to remove cesium or strontium from the pool cell in the event of a capsule failure. The emergency system is call the WESF Emergency Ion Exchange System and the packaging is called the WESF ion exchange module (WIXM). The packaging system will meet the onsite transportation requirements for a Type B, highway route controlled quantity package as well as disposal requirements for Category 3 waste

  1. Highest manageable level of radioactivity in the waste storage facilities of power plants

    International Nuclear Information System (INIS)

    This project presents and discusses an investigation of the highest level of radioactivity possible to handle in the waste storage facilities. The amount of radioactivity, about 0.1% of the fuel inventory, is the same in both of the cases but the amount of water is very different. The hypothetical accident was supposed to be damage of the reactor fuel caused by loss of coolant. (K.A.E.)

  2. The Gorleben situation. Radwaste interim storage facility, conditioning pilot plant, exploration mine

    International Nuclear Information System (INIS)

    The radwaste interim storage facility has been in operation since 1983, the conditioning pilot plant is under construction, and exploration work is well under way in the mine for preparing the site for service as a radwaste repository. The name Gorleben practically has become a synonym term for ultimate radwaste disposal strategy, and for determined opposition against atomic energy. Dagmar Roehrlich has been on site on behalf of Energie Spektrum and reports the current situation. (orig.)

  3. Hanford environment as related to radioactive waste burial grounds and transuranium waste storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D.J.; Isaacson, R.E.

    1977-06-01

    A detailed characterization of the existing environment at Hanford was provided by the U.S. Energy Research and Development Administration (ERDA) in the Final Environmental Statement, Waste Management Operations, Hanford Reservation, Richland, Washington, December 1975. Abbreviated discussions from that document are presented together with current data, as they pertain to radioactive waste burial grounds and interim transuranic (TRU) waste storage facilities. The discussions and data are presented in sections on geology, hydrology, ecology, and natural phenomena. (JRD)

  4. The role of interim storage facilities in the nuclear waste management policy of Germany

    International Nuclear Information System (INIS)

    The article discusses the role of interim storage of spent fuel elements in the current nuclear waste management policy in Germany, and possible demand for additional interim storage facilities in the future, as a consequence of the shift in the radioactive waste disposal concept and the nuclear power opt-out policy of the Federal Government. Success or failure of the consensus on the nuclear power phase-out strategy, agreed between the Federal Government and the nuclear power industry on 14 June 2000, hinges not only but essentially on the availability of sufficient interim storage facilities for spent fuel elements accrued over the negotiated remaining operating periods of nuclear power plants. The NPP operators say the present radioactive waste management concept has to be put on a different basis and needs amending in response to the change in energy policy. For the electric utilities, the crucial test is whether the Federal Government will be able to fulfill their promise made during the consensus negotiations, namely that there will be no premature shutdowns of nuclear power plants because of a bottleneck in spent fuel storage capacity. (orig./CB)

  5. Investigation of Storage Options for Scientific Computing on Grid and Cloud Facilities

    International Nuclear Information System (INIS)

    In recent years, several new storage technologies, such as Lustre, Hadoop, OrangeFS, and BlueArc, have emerged. While several groups have run benchmarks to characterize them under a variety of configurations, more work is needed to evaluate these technologies for the use cases of scientific computing on Grid clusters and Cloud facilities. This paper discusses our evaluation of the technologies as deployed on a test bed at FermiCloud, one of the Fermilab infrastructure-as-a-service Cloud facilities. The test bed consists of 4 server-class nodes with 40 TB of disk space and up to 50 virtual machine clients, some running on the storage server nodes themselves. With this configuration, the evaluation compares the performance of some of these technologies when deployed on virtual machines and on “bare metal” nodes. In addition to running standard benchmarks such as IOZone to check the sanity of our installation, we have run I/O intensive tests using physics-analysis applications. This paper presents how the storage solutions perform in a variety of realistic use cases of scientific computing. One interesting difference among the storage systems tested is found in a decrease in total read throughput with increasing number of client processes, which occurs in some implementations but not others.

  6. Design, construction and commissioning of the new solid waste management and storage facilities of Ignalina NPP, Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Goehring, R.; Wenninger, K. [RWE NUKEM GmbH, Alzenau (Germany)

    2006-04-15

    The contract for the design, construction and commissioning (turn-key) of the New Solid Waste Management and Storage Facilities (SWMSF) has been awarded to RWE NUKEM GmbH. The contract was signed on the 30.11.2005. The New Solid Waste Management and Storage Facilities (SWMSF) are financed by the Ignalina Decommissioning Support Fund which is managed by European Bank for Reconstruction and Development (EBRD). The new facilities are required on the Ignalina Nuclear Power Plant (INPP) in order to support ongoing decomissioning work, including removal of waste from existing waste storage buildings. (orig.)

  7. Zwilag intermediate storage facility Wuerenlingen AG (CH). 25 years existence of the company, 15 years operational experience

    International Nuclear Information System (INIS)

    Wastes with high toxicity from chemistry, pharmaceutics, process engineering, automotive and electrical engineering that comply with the requirements of an underground disposal facility (UTD) can directly be delivered to the UTD for final disposal. Radioactive wastes may not be brought into the UTD for final disposal. Compared to chemical wastes the radioactive wastes lose their toxicity faster but the after-heat generation could damage the surrounding host rock. Therefore it is required that high-level radioactive wastes are stored in a so called intermediate storage facility. The article describes the intermediate storage and conditioning of radioactive wastes using the example of the Swiss Zwilag intermediate storage facility Wuerenlingen AG.

  8. Hazardous Material Storage Facilities and Sites, Hazardous Waste Material Storage Sites at Maryland Transit Administrations Washington Boulevard Facility e.g. Crusher, Universal Waste Battery, Published in 2008, 1:4800 (1in=400ft) scale, Maryland Transit Administration.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Hazardous Material Storage Facilities and Sites dataset, published at 1:4800 (1in=400ft) scale, was produced all or in part from Field Observation information...

  9. Storage fee analysis for a nuclear waste terminal storage facility. Final report

    International Nuclear Information System (INIS)

    A model was developed for determining a pricing schedule designed to recover federal government costs incurred in the development, design, construction, operation, decommissioning, and surveillance of a federal repository for high-level waste generated by the commercial nuclear power industry. As currently constructed, the model computes current dollar prices on a yearly basis for a single unit charge or a split fee based upon two user-provided quantity flows. Over the period of facility operation, the computed-cost schedule shows variability on a year-to-year basis only within specified ranges. The model uses as basic input data: cost schedule for the federal repository; quantity flow schedule for each factor to be charged; schedule for escalation rate, discount rate, and interest rate; and fraction of costs to be recovered on each quantity flow if the split-fee option is used. The model allows testing of these variables in order to determine the relative significance of each component with regard to cost to, and impact on, the nuclear power industry. Another feature of the model is its versatility. Not only is the user able to specify the percent of total costs to be covered by each method of fee assessment listed above but also the user can specify a revenue-cost ratio, an option that would prove useful in trying to assess the general uncertainty involved when dealing in the future. In addition, the model accepts either current-dollar or constant-dollar cost measures, and in the case of the latter escalates the costs with user-provided assumptions

  10. Waste management facility accident analysis (WASTE ACC) system: software for analysis of waste management alternatives

    International Nuclear Information System (INIS)

    This paper describes the Waste Management Facility Accident Analysis (WASTEunderscoreACC) software, which was developed at Argonne National Laboratory (ANL) to support the US Department of Energy's (DOE's) Waste Management (WM) Programmatic Environmental Impact Statement (PEIS). WASTEunderscoreACC is a decision support and database system that is compatible with Microsoft reg-sign Windows trademark. It assesses potential atmospheric releases from accidents at waste management facilities. The software provides the user with an easy-to-use tool to determine the risk-dominant accident sequences for the many possible combinations of process technologies, waste and facility types, and alternative cases described in the WM PEIS. In addition, its structure will allow additional alternative cases and assumptions to be tested as part of the future DOE programmatic decision-making process. The WASTEunderscoreACC system demonstrates one approach to performing a generic, systemwide evaluation of accident risks at waste management facilities. The advantages of WASTEunderscoreACC are threefold. First, the software gets waste volume and radiological profile data that were used to perform other WM PEIS-related analyses directly from the WASTEunderscoreMGMT system. Second, the system allows for a consistent analysis across all sites and waste streams, which enables decision makers to understand more fully the trade-offs among various policy options and scenarios. Third, the system is easy to operate; even complex scenario runs are completed within minutes

  11. The low to intermediate activity and short living waste storage facility. For a controlled management of radioactive wastes

    International Nuclear Information System (INIS)

    Sited at about 50 km of Troyes (France), the Aube facility started in 1992 and has taken over the Manche facility for the surface storage of low to intermediate and short living radioactive wastes. The Aube facility (named CSFMA) is the answer to the safe management of these wastes at the industrial scale and for 50 years onward. This brochure presents the facility specifications, the wastes stored at the center, the surface storage concept, the processing and conditioning of waste packages, and the environmental monitoring performed in the vicinity of the site. (J.S.)

  12. SNL Storage Facility Fire Environment Experiment Data for Model Validation and Development

    International Nuclear Information System (INIS)

    The development of validated numerical tools to predict the thermal hazard posed by a fuel fire that results from an aircraft or ground transportation accident is a goal of the Fuel Fire Technology Base Program. These validated tools support Defense Threat Reduction Agency (DTRA) probabilistic Weapon System Safety Assessments (WSSA). Two types of tools are being developed to support this type of activity: (1) tools that model the detailed physics of the problem (e.g., fire field models); and (2) tools that model the dominant phenomena (e.g., the risk assessment compatible fire models (RACFMs)). RACFMs are tailored to be compatible with the methodology of a probabilistic WSSA. A large-scale fire testing program has been established to obtain experimental data to (1) develop and calibrate RACFMs, (2) validate and further develop fire field models, (3) assess the fire threat to actual systems of interest and, (4) provide archival data for future assessments. This report describes nine full-scale enclosure pool fire experiments (JP8 fueled) that were conducted at the Sandia National Laboratories (SNL) Lurance Canyon Burn Site in the Building 9830 'Igloo' Facility. Experiment and hardware requirements, the test facility, instrumentation, and a complete description of each experiment are provided herein. The primary purpose of the test series was to furnish experimental data for validating compartment fire models that are being developed to predict the abnormal thermal environment in a storage facility/aircraft accident situation. Fires of interest in the storage and maintenance facilities are primarily hydrocarbon pool fires that could occur as a result of an aircraft engine penetrating the facility during an accident. The models, in turn, are to be used to assess the thermal hazard posed to stored weapons within the facility. (author)

  13. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment ampersand storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage ampersand treatment facilities

    International Nuclear Information System (INIS)

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory's storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations

  14. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sasser, K.

    1994-06-01

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

  15. Sampling and analysis of radioactive liquid wastes and sludges in the Melton Valley and evaporator facility storage tanks at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Sears, M.B.; Botts, J.L.; Ceo, R.N.; Ferrada, J.J.; Griest, W.H.; Keller, J.M.; Schenley, R.L.

    1990-09-01

    The sampling and analysis of the radioactive liquid wastes and sludges in the Melton Valley Storage Tanks (MVSTs), as well as two of the evaporator service facility storage tanks at ORNL, are described. Aqueous samples of the supernatant liquid and composite samples of the sludges were analyzed for major constituents, radionuclides, total organic carbon, and metals listed as hazardous under the Resource Conservation and Recovery Act (RCRA). Liquid samples from five tanks and sludge samples from three tanks were analyzed for organic compounds on the Environmental Protection Agency (EPA) Target Compound List. Estimates were made of the inventory of liquid and sludge phases in the tanks. Descriptions of the sampling and analytical activities and tabulations of the results are included. The report provides data in support of the design of the proposed Waste Handling and Packaging Plant, the Liquid Low-Level Waste Solidification Project, and research and development activities (R D) activities in developing waste management alternatives. 7 refs., 8 figs., 16 tabs.

  16. Dose reduction through automation of nuclear weapons dismantlement and storage procedures at the Department of Energy's Pantex Facility

    International Nuclear Information System (INIS)

    With the end of the Cold War and the subsequent break up of the Soviet Union, the number of weapons in the nuclear stockpile now greatly exceeds any foreseeable future need. To compensate for this excess an estimated 20,000 nuclear warheads have been earmarked for dismantlement and storage at the Department of Energy's Pantex Plant near Amarillo, Texas. It is anticipated that the majority of these warheads will arrive at the Pantex facility by the year 2000. At that time, it is estimated that current dismantlement and inventory procedures will not be adequate to control worker radiation exposure within administrative and federal dose limits. To control these exposures alternate approaches to dismantlement and inventory must be developed. One attractive approach is to automate as many activities as possible, thus reducing worker exposure. To facilitate automation of dismantlement and storage procedures, current procedures were investigated in terms of collective dose to workers, time to completion, ease of completion, and cost of automation for each task. A cost-benefit comparison was then performed in order to determine which procedures would be most cost-effective to automate

  17. Effect of process-dependent parameters of the handling-and-storage facility operation on the cargo handling cost

    OpenAIRE

    Шраменко, Наталя Юріївна

    2015-01-01

    Analysis of the handling-and-storage facility operation revealed the disadvantages of the technology that is related to the non-consideration of incoming cargo traffic variations in the planning and organization of industrial activity.The criterion of the handling-and-storage facility operation that presents unit costs for cargo handling has been formalized. The criterion makes it possible to take into account the cargo owner's costs associated with downtime of vehicles waiting for service an...

  18. Effects of temperature on concrete cask in a dry storage facility for spent nuclear fuels

    International Nuclear Information System (INIS)

    In the dry storage of spent nuclear fuels,concrete cask serves both as a shielding and a structural containment. The concrete in the storage facility is expected to endure the decay heat of the spent nuclear fuel during its service life. Thus, effects of the sustaining high temperature on concrete material need be evaluated for safety of the dry storage facility. In this paper, we report an experimental program aimed at investigating possible high temperature effects on properties of concrete, with emphasis on the mechanical stability, porosity,and crack-resisting ability of concrete mixes prepared using various amounts of Portland cement, fly ash, and blast furnace slag. The experimental results obtained from concrete specimens exposed to a temperature of 94 degree C for 90 days indicate that: (1) compressive strength of the concrete remains practically unchanged; (2) the ultrasonic pulse velocity, and dynamic modulus of elasticity of the concrete decrease in early stage of the high-temperature exposure,and gradually become stable with continuing exposure; (3) shrinkage of concrete mixes exhibits an increase in early stage of the exposure and does not decrease further with time; (4) concrete mixes containing pozzolanic materials,including fly ash and blast furnace slag, show better temperature-resisting characteristics than those using only Portland cement. (authors)

  19. Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities

    International Nuclear Information System (INIS)

    A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

  20. CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I

    International Nuclear Information System (INIS)

    The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP

  1. Waste Encapsulation and Storage Facility (WESF) Basis for Interim Operation (BIO)

    Energy Technology Data Exchange (ETDEWEB)

    COVEY, L.I.

    2000-11-28

    The Waste Encapsulation and Storage Facility (WESF) is located in the 200 East Area adjacent to B Plant on the Hanford Site north of Richland, Washington. The current WESF mission is to receive and store the cesium and strontium capsules that were manufactured at WESF in a safe manner and in compliance with all applicable rules and regulations. The scope of WESF operations is currently limited to receipt, inspection, decontamination, storage, and surveillance of capsules in addition to facility maintenance activities. The capsules are expected to be stored at WESF until the year 2017, at which time they will have been transferred for ultimate disposition. The WESF facility was designed and constructed to process, encapsulate, and store the extracted long-lived radionuclides, {sup 90}Sr and {sup 137}Cs, from wastes generated during the chemical processing of defense fuel on the Hanford Site thus ensuring isolation of hazardous radioisotopes from the environment. The construction of WESF started in 1971 and was completed in 1973. Some of the {sup 137}Cs capsules were leased by private irradiators or transferred to other programs. All leased capsules have been returned to WESF. Capsules transferred to other programs will not be returned except for the seven powder and pellet Type W overpacks already stored at WESF.

  2. Waste Encapsulation and Storage Facility (WESF) Basis for Interim Operation (BIO)

    International Nuclear Information System (INIS)

    The Waste Encapsulation and Storage Facility (WESF) is located in the 200 East Area adjacent to B Plant on the Hanford Site north of Richland, Washington. The current WESF mission is to receive and store the cesium and strontium capsules that were manufactured at WESF in a safe manner and in compliance with all applicable rules and regulations. The scope of WESF operations is currently limited to receipt, inspection, decontamination, storage, and surveillance of capsules in addition to facility maintenance activities. The capsules are expected to be stored at WESF until the year 2017, at which time they will have been transferred for ultimate disposition. The WESF facility was designed and constructed to process, encapsulate, and store the extracted long-lived radionuclides, 90Sr and 137Cs, from wastes generated during the chemical processing of defense fuel on the Hanford Site thus ensuring isolation of hazardous radioisotopes from the environment. The construction of WESF started in 1971 and was completed in 1973. Some of the 137Cs capsules were leased by private irradiators or transferred to other programs. All leased capsules have been returned to WESF. Capsules transferred to other programs will not be returned except for the seven powder and pellet Type W overpacks already stored at WESF

  3. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    International Nuclear Information System (INIS)

    As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to

  4. Hazard Evaluation for Storage of Spent Nuclear Fuel (SNF) Sludge at the Solid Waste Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    SCHULTZ, M.V.

    2000-08-22

    As part of the Spent Nuclear Fuel (SNF) storage basin clean-up project, sludge that has accumulated in the K Basins due to corrosion of damaged irradiated N Reactor will be loaded into containers and placed in interim storage. The Hanford Site Treatment Complex (T Plant) has been identified as the location where the sludge will be stored until final disposition of the material occurs. Long term storage of sludge from the K Basin fuel storage facilities requires identification and analysis of potential accidents involving sludge storage in T Plant. This report is prepared as the initial step in the safety assurance process described in DOE Order 5480.23, Nuclear Safety Analysis Reports and HNF-PRO-704, Hazards and Accident Analysis Process. This report documents the evaluation of potential hazards and off-normal events associated with sludge storage activities. This information will be used in subsequent safety analyses, design, and operations procedure development to ensure safe storage. The hazards evaluation for the storage of SNF sludge in T-Plant used the Hazards and Operability Analysis (HazOp) method. The hazard evaluation identified 42 potential hazardous conditions. No hazardous conditions involving hazardous/toxic chemical concerns were identified. Of the 42 items identified in the HazOp study, eight were determined to have potential for onsite worker consequences. No items with potential offsite consequences were identified in the HazOp study. Hazardous conditions with potential onsite worker or offsite consequences are candidates for quantitative consequence analysis. The hazardous conditions with potential onsite worker consequences were grouped into two event categories, Container failure due to overpressure - internal to T Plant, and Spill of multiple containers. The two event categories will be developed into accident scenarios that will be quantitatively analyzed to determine release consequences. A third category, Container failure due to

  5. Development of evaluation method for heat removal design of dry storage facilities. Pt. 4. Numerical analysis on vault storage system of cross flow type

    International Nuclear Information System (INIS)

    On the basis of the result of the heat removal test on vault storage system of cross flow type using the 1/5 scale model, an evaluation method for the heat removal design was established. It was composed of the numerical analysis for the convection phenomena of air flow inside the whole facility and that for the natural convection and the detailed turbulent mechanism near the surface of the storage tube. In the former analysis, air temperature distribution in the storage area obtained by the calculation gave good agreement within ±3degC with the test result. And fine turbulence models were introduced in the latter analysis to predict the separation flow in the boundary layer near the surface of the storage tube and the buoyant flow generated by the heat from the storage tube. Furthermore, the properties of removing the heat in a designed full-scale storage facility, such as flow pattern in the storage area, temperature and heat transfer rate of the storage tubes, were evaluated by using each of three methods, which were the established numerical analysis method, the experimental formula demonstrated in the heat removal test and the conventional evaluation method applied to the past heat removal design. As a result, the safety margin and issues included in the methods were grasped, and the measures to make a design more rational were proposed. (author)

  6. Distributed generation, storage, demand response and energy efficiency as alternatives to grid capacity enhancement

    International Nuclear Information System (INIS)

    The need for investment in capital intensive electricity networks is on the rise in many countries. A major advantage of distributed resources is their potential for deferring investments in distribution network capacity. However, utilizing the full benefits of these resources requires addressing several technical, economic and regulatory challenges. A significant barrier pertains to the lack of an efficient market mechanism that enables this concept and also is consistent with business model of distribution companies under an unbundled power sector paradigm. This paper proposes a market-oriented approach termed as “contract for deferral scheme” (CDS). The scheme outlines how an economically efficient portfolio of distributed generation, storage, demand response and energy efficiency can be integrated as network resources to reduce the need for grid capacity and defer demand driven network investments. - Highlights: • The paper explores a practical framework for smart electricity distribution grids. • The aim is to defer large capital investments in the network by utilizing and incentivising distributed generation, demand response, energy efficiency and storage as network resources. • The paper discusses a possible new market model that enables integration of distributed resources as alternative to grid capacity enhancement

  7. Facile fabrication of one-dimensional mesoporous titanium dioxide composed of nanocrystals for lithium storage

    International Nuclear Information System (INIS)

    Titanium dioxide (TiO2) has received increasing attention as promising anode for lithium ion batteries because it offers a distinct safety advantage in comparison to commercialized graphite anodes, whereas it also suffer from the drawbacks of low practical capacity and relatively low electronic conductivity. Herein, one-dimensional mesoporous anatase TiO2 composed of nanocrystals prepared by a facile procedure is reported for the first time. Such peculiar architecture and intrinsical mesoporous can effectively improve pseudocapacitance charge storage, increase contact interface between the active materials and electrolyte, and enhance the structure stability during cycling, therefore contributing to good lithium storage and excellent cycling stability. A reversible capacity of 202.9 mAhg−1is obtained at 30 mAg−1 after 70 cycles. More importantly, 151 mAhg−1 can be obtained at 200 mAg−1 even after 500 cycles

  8. The Acceleration and Storage of Radioactive Ions for a Beta-Beam Facility

    CERN Document Server

    Lindroos, M; Napoly, O; Payet, J; Benedikt, Michael; Butler, P; Garoby, R; Hancock, S; Köster, U; Lindroos, M; Magistris, M; Nilsson, T; Wenander, F; Blondel, A; Gilardoni, S S; Boine-Frankenheim, O; Franzke, B; Höllinger, R; Steck, Markus; Spiller, P J; Weick, H; Burguet, J; Gómez-Cadenas, J J; Hernández, P; Laune, B; Müller, A; Sortais, P; Villari, A C C; Volpe, C; Facco, A; Mezzetto, Mauro; Palladino, V; Pisent, A; Zucchelli, P; Delbar, T; Ryckewaert, G; Chartier, M; Prior, C; Reistad, D; Baartman, R A; Jansson, A

    2004-01-01

    The term beta-beam has been coined for the production of a pure beam of electron neutrinos or their antiparticles through the decay of radioactive ions circulating in a storage ring. This concept requires radioactive ions to be accelerated to as high Lorentz  as 150. The neutrino source itself consists of a storage ring for this energy range, with long straight sections in line with the experiment(s). Such a decay ring does not exist at CERN today, nor does a high-intensity proton source for the production of the radioactive ions. Nevertheless, the existing CERN accelerator infrastructure could be used as this would still represent an important saving for a beta-beam facility.

  9. Site safety progress review of spent fuel central interim storage facility. Final report

    International Nuclear Information System (INIS)

    Following the request of the Czech Power Board (CEZ) and within the scope of the Technical Cooperation Project CZR/9/003, a progress review of the site safety of the Spent Fuel Central Interim Storage Facility (SFCISF) was performed. The review involved the first two stages of the works comprising the regional survey and identification of candidate sites for the underground and surface storage options. Five sites have been identified as a result of the previous works. The following two stages will involved the identification of the preferred candidate sites for the two options and the final site qualification. The present review had the purpose of assessing the work already performed and making recommendations for the next two stages of works

  10. Holographic data storage crystals for the LDEF. [long duration exposure facility

    Science.gov (United States)

    Callen, W. Russell; Gaylord, Thomas K.

    1992-01-01

    Lithium niobate is a significant electro-optic material, with potential applications in ultra high capacity storage and processing systems. Lithium niobate is the material of choice for many integrated optical devices and holographic mass memory systems. For crystals of lithium niobate were passively exposed to the space environment of the Long Duration Exposure Facility (LDEF). Three of these crystals contained volume holograms. Although the crystals suffered the surface damage characteristics of most of the other optical components on the Georgia Tech tray, the crystals were recovered intact. The holograms were severely degraded because of the lengthy exposure, but the bulk properties are being investigated to determine the spaceworthiness for space data storage and retrieval systems.

  11. Corrosion of aluminium-clad spent fuel in LVR-15 Research Reactor storage facilities

    International Nuclear Information System (INIS)

    This report documents the work performed under the IAEA Coordinated Research Project (CRP) on corrosion of the research reactor aluminium-clad spent fuel in water in the Nuclear Research Institute Rez. The aim of the project was to evaluate the corrosion of coupons of aluminium alloys used as cladding material of research reactor fuel elements, upon exposure to the water on the spent fuel storage basins. The corrosion of coupons exposed to two storage facilities at our Institute was investigated. Test racks were delivered by the IAEA and these contained coupons of two aluminium alloys, AA 6061 and SZAV-1. The racks also contained bimetallic couples consisting of aluminium alloy and stainless steel coupons. Rolled and extruded AA 6061 coupons were also tested. The single coupons, bimetallic couples and coupons with crevice couples were immersed in the at-reactor basin (ARB) and in the high-level waste pool (HLW). The chemical parameters of water in the two storage facilities were monitored and the extent of sedimentation of solids was measured. The ionic impurities were mainly Cl- and SO42- and their contents were 2 -15 μg/l in the HLW pool and about 20-250 μg/l in ARB. The iron content was below 2 μg/l in both facilities. After two years of exposure, pitting of the coupons was evaluated. Pits were observed mainly on the surfaces of single coupons and on the outer and inner surfaces of bimetallic and crevices coupons. No correlation was found between pitting and the type of aluminium alloy or between rolled and extruded materials. In the bimetallic couples, contact with stainless steel coupons did not have any affect on localized corrosion of the Al coupons. The pit depths were less than 50 μm on most of the coupon surfaces. Data obtained at this Institute should be compared with the results of other participants of this CRP. (author)

  12. Experience from the operation of the Swedish Central Interim Storage Facility for Spent Nuclear Fuel, CLAB

    International Nuclear Information System (INIS)

    Currently, about 50% of the electric power in Sweden is generated by means of nuclear power. The Swedish nuclear programme comprises 12 plants. According to political decisions, no more nuclear power plants will be built and the existing plants will not be operated beyond the year 2010. The programme will give rise to not more than 7800 t U of spent fuel, which will be directly disposed of in the crystalline bedrock without reprocessing. A keystone in the spent fuel management strategy is the Central Interim Storage Facility for Spent Nuclear Fuel, CLAB. After intensive pre-project work, the licensing of CLAB according to the Building, Environment Protection and Atomic Energy Acts took place in 1978-1979. After a total licensing time of about 20 months, the last permit was obtained in August 1979. By August 1994, CLAB had received and unloaded some 720 fuel transport casks, corresponding to about 2000 t U, and 60 casks containing highly active core components. The performance of the plant has been very satisfactory and with increasing experience it has been possible to reduce the operating and maintenance costs. The extensive efforts during the design phase have resulted in a collective dose of 25-30% of the dose calculated in the final safety report. Owing to a low activity release from the fuel and optimized management of the used water filtering agents, the number of waste packages emanating from CLAB has been less than 10% of what was originally expected. The activity release to air and water from the facility during the first five years of operation has been around 0.01% of the permissible release. In order to postpone the building of additional storage pools, new storage canisters have been developed which has increased the storage capacity from 3000 to 5000 t U. (author). 1 fig

  13. Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia

    International Nuclear Information System (INIS)

    The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted waste monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal Ministry of Economics and Labour (BMWi). On the Russian side the Kurchatov Institute holds the project management of the long-term interim storage facility in Sayda Bay, whilst the Nerpa Shipyard, which is about 25 km away from the storage facility, is dismantling the submarines and preparing the reactor compartments for long-term interim storage. The technical monitoring of the German part of this project, being implemented by BMWi, is the responsibility of the Federal Institute for Materials Research and Testing (BAM). This paper gives an overview of the German-Russian project and a brief description of solutions for nuclear submarine disposal in other countries. At Nerpa shipyard, being refurbished with logistic and technical support from Germany, the reactor compartments are sealed by welding, provided with biological shielding, subjected to surface treatment and conservation measures. Using floating docks, a tugboat tows the reactor compartments from Nerpa shipyard to the interim storage facility at Sayda Bay where they will be left on the on-shore concrete

  14. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S. origin from foreign research reactors to the United States. As of December 1999, over 22% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These ∼2650 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed the L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into the L-Area in April 1997 and approximately 105 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment will be explained to show

  15. Magnetic measurement system for cooling storage ring of heavy ion research facility in Lanzhou

    International Nuclear Information System (INIS)

    Magnetic measurement system is an indispensable part of National Scientific Major-project Cooling Storage Ring of Heavy Ion Research Facility in Lanzhou (HIRFL-CSR). Three measurement systems, Hall probe mapping, integral coils and harmonic coils system were developed. The structure and parameters of main devices were described in details in the paper. And the manufacturing technics and the checking results were also involved. By means of a long time repeat testing, it is proved that the repeatability and stability of the systems match the requirements of CSR. The systems are applying in CSR project now. (author)

  16. Power Hardware-in-the-Loop (PHIL) Testing Facility for Distributed Energy Storage (Poster)

    Energy Technology Data Exchange (ETDEWEB)

    Neubauer.J.; Lundstrom, B.; Simpson, M.; Pratt, A.

    2014-06-01

    The growing deployment of distributed, variable generation and evolving end-user load profiles presents a unique set of challenges to grid operators responsible for providing reliable and high quality electrical service. Mass deployment of distributed energy storage systems (DESS) has the potential to solve many of the associated integration issues while offering reliability and energy security benefits other solutions cannot. However, tools to develop, optimize, and validate DESS control strategies and hardware are in short supply. To fill this gap, NREL has constructed a power hardware-in-the-loop (PHIL) test facility that connects DESS, grid simulator, and load bank hardware to a distribution feeder simulation.

  17. An automatically controlled system for waste transport in low level nuclear waste storage facilities

    International Nuclear Information System (INIS)

    Kobe Steel has developed and manufactured a fully automatic remote-controlled system for the storage of up to 42 000 waste drum packages discharged from nuclear reprocessing facilities. The system includes two forklifts and an elevator both of which are controlled via a remote control center. The forklifts can transport up to 4 ton waste packages. The elevator can transport a forklift carrying a maximum weight package. The system also includes a rescue vehicle that can be manually operated at a distance from a remote station using ITV cameras. (author)

  18. Improvement of numerical simulation methods on safety assessment of the spent fuel storage facility

    International Nuclear Information System (INIS)

    Improvement of numerical simulation methods on safety assessment of the spent fuel storage facility is one of main objectives of JNES activities. For the thermal and structural analyses, the radiative heat transfer analysis code S-FOKS has been developed to reduce computing time and to avoid using large memory area. In order to simulate the specular reflection, a new model (called 'model-2') is planned to install to S-FOKS code. The theoretical values with the specular reflection in simple geometry were lead to verify S-FOKS model-2. (author)

  19. Ventilation and exhaust ducts for dry storage facilities with self-heating radioactive materials

    International Nuclear Information System (INIS)

    The storage facilities are cooled by natural convection. In order to achieve this, the air inlet and outlet openings or ducts for the PWR and BWR fuel store are arranged at the level of the roof structure. There are two types of air inlet openings arranged on top and on the sides respectively but having got common inlet ducts. Air supply is improved by means of baffle noses, baffle edges, and baffle plates. The exhaust air ducts terminate near the roof structure, the openings having got dropping edges, protective sills and separating plates. (orig./PW)

  20. An information management system for a spent nuclear fuel interim storage facility.

    Energy Technology Data Exchange (ETDEWEB)

    Finch, Robert J.; Chiu, Hsien-Lang (Taiwan Power Co., Taipei, 10016 Taiwan); Giles, Todd; Horak, Karl Emanuel; Jow, Hong-Nian (Jow International, Kirkland, WA)

    2010-12-01

    We describe an integrated information management system for an independent spent fuel dry-storage installation (ISFSI) that can provide for (1) secure and authenticated data collection, (2) data analysis, (3) dissemination of information to appropriate stakeholders via a secure network, and (4) increased public confidence and support of the facility licensing and operation through increased transparency. This information management system is part of a collaborative project between Sandia National Laboratories, Taiwan Power Co., and the Fuel Cycle Materials Administration of Taiwan's Atomic Energy Council, which is investigating how to implement this concept.

  1. An information management system for a spent nuclear fuel interim storage facility

    International Nuclear Information System (INIS)

    We describe an integrated information management system for an independent spent fuel dry-storage installation (ISFSI) that can provide for (1) secure and authenticated data collection, (2) data analysis, (3) dissemination of information to appropriate stakeholders via a secure network, and (4) increased public confidence and support of the facility licensing and operation through increased transparency. This information management system is part of a collaborative project between Sandia National Laboratories, Taiwan Power Co., and the Fuel Cycle Materials Administration of Taiwan's Atomic Energy Council, which is investigating how to implement this concept.

  2. Spatial distribution of stored grain insects in a rice storage and processing facility in Brazil

    OpenAIRE

    Lazzari, F. N.; Lazzari, F. A.; Lazzari, S. M. N.; Ceruti, F. C.

    2010-01-01

    This study describes the spatial distribution of stored product insects captured biweekly using foodbaited cage traps in a large rice storage and processing facility, in the state of Rio Grande do Sul, Brazil. Monitoring started in August 2009 and will be carried out for 1 year, the first 5 months of sampling being presented in this study. From end of August 2009 until the end of December 2009, a total of 9893 insects were captured in the 99 cage traps. The most abundant species were: Carpop...

  3. Radiological considerations regarding an alternate method for the placement of intermediate impact absorbers at the Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    This report documents radiological considerations arising from the proposed implementation of an alternate method for intermediate impact absorber placement at the Canister Storage Building (CSB). These considerations include revising the dose rate estimate, at deck level over an open storage tube and outlining the administrative controls necessary for this implementation. Currently, the MCO Handling Machine (MHM) is used to install the intermediate impact absorbers. The proposed alternative would utilize a mobile crane, thus freeing up the MHM to handle the movement of MCOs within the CSB

  4. Retrieval and conditioning of high level radioactive solid waste from pit-type storage facilities

    International Nuclear Information System (INIS)

    A city radioactive waste temporary storage facility was operated for many years and aged seriously. In the 1970s, some high level radioactive solid waste (HLW) was stored in this facility because of bad management, which threatens the environment safety and should be retrieved and conditioned as soon as possible. According to the real condition in site, a retrieval technical process for HLW utilizing 'robot-airproof work cell' was employed the Department of Radioactive Waste Management, CIAE. The HLW was located in the No. 17 pit through contaminated level and detected hot-spot. After the mock-up test, the retrieval technical process was optimized. Finally, the HLW was successfully retrieved and conditioned in remote control way. (authors)

  5. Characterization of two WESF [Waste Encapsulation and Storage Facility] capsules after five years of service

    International Nuclear Information System (INIS)

    Two Waste Encapsulation and Storage Facility (WESF) 137Cs capsules have been analyzed destructively after five years of service in the Sandia Irradiator for Dried Sewage Solids (SIDSS). The program concentrated on studies of the inner capsule, inner capsule weld areas, and analysis of the CsCl salt. No measurable corrosion was observed on the capsule wall or welds after the five years in the SIDSS Facility. The operating temperatures of the inner capsule wall were calculated to be between 140 and 180/degree/C. Radiochemistry and isotopic analyses provided data for specific activity calculations. There was good correlation between the measured calorimetry of the capsules before sectioning, 53 and 55 kCi, and the activity calculations, 54 and 59 kCi, respectively. 21 refs., 43 figs., 18 tabs

  6. Construction of mixed waste storage RCRA facilities, Buildings 7668 and 7669: Environmental assessment

    International Nuclear Information System (INIS)

    The Department of Energy has prepared an environmental assessment, DOE/EA-0820, to assess the potential environmental impacts of constructing and operating two mixed waste Resource Conservation and Recovery Act (RCRA) storage facilities. The new facilities would be located inside and immediately west of the security-fenced area of the Oak Ridge National Laboratory Hazardous Waste Management Area in Melton Valley, Tennessee. Based on the analyses in the environmental assessment, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required, and the Department is issuing this finding of no significant impact

  7. An Evaluation Model for Tailings Storage Facilities Using Improved Neural Networks and Fuzzy Mathematics

    Directory of Open Access Journals (Sweden)

    Sen Tian

    2014-01-01

    Full Text Available With the development of mine industry, tailings storage facility (TSF, as the important facility of mining, has attracted increasing attention for its safety problems. However, the problems of low accuracy and slow operation rate often occur in current TSF safety evaluation models. This paper establishes a reasonable TSF safety evaluation index system and puts forward a new TSF safety evaluation model by combining the theories for the analytic hierarchy process (AHP and improved back-propagation (BP neural network algorithm. The varying proportions of cross validation were calculated, demonstrating that this method has better evaluation performance with higher learning efficiency and faster convergence speed and avoids the oscillation in the training process in traditional BP neural network method and other primary neural network methods. The entire analysis shows the combination of the two methods increases the accuracy and reliability of the safety evaluation, and it can be well applied in the TSF safety evaluation.

  8. Facility site check report transportation safeguards divsision (TSD) underground storage tanks 2334-U and 2335-U at Building 9714

    International Nuclear Information System (INIS)

    This document presents an overview of the underground storage tank (UST)-related events that have taken place at the Transportation Safeguards Division (TSD) Facility (Facility ID 0-730168). The TSD facility is managed by Lockheed Martin Energy Systems, Inc. (LMES) for the U.S. Department of Energy (DOE), and is used to maintain and fuel specialty fleet vehicles. The facility is located approximately one mile east of the K-25 site at the intersection of Blair Road and the Oak Ridge Turnpike (Hwy 58). The location of the USTs at the TSD facility are illustrated

  9. Analysis of removal of residual decay heat from interim storage facilities by means of the CFD program FLUENT

    International Nuclear Information System (INIS)

    Within the scope of nuclear licensing procedures of on-site interim storage facilities for dual purpose casks it is necessary, among other things, to provide proof of sufficient removal of the residual decay heat emitted by the casks. The results of the analyses performed for this purpose define e.g. the boundary conditions for further thermal analyses regarding the permissible cask component temperatures or the maximum permissible temperatures of the fuel cladding tubes of the fuel elements stored in the casks. Up to now, for the centralized interim storage facilities in Germany such analyses were performed on the basis of experimental investigations using scaled-down storage geometries. In the engineering phase of the Lingen on-site interim storage facility, proof was furnished for the first time using the CFD (computational fluid dynamics) program FLUENT. The program FLUENT is an internationally recognized and comprehensively verified program for the calculation of flow and heat transport processes. Starting from a brief discussion of modeling and the different boundary conditions of the computation, this contribution presents various results regarding the temperatures of air, cask surfaces and storage facility components, the mass flows through the storage facility and the heat transfer at the cask surface. The interface point to the cask-specific analyses is defined to be the cask surface

  10. Habog: a new multi-purpose, safe and economic storage facility for Covra in the Netherlands

    International Nuclear Information System (INIS)

    COVRA's HABOG facility has been under construction since spring 1999, alter a three-year design phase during which the facility was devised to meet different stringent requirements: - ability to store multiple products: reprocessing waste, particularly glasses; research reactor fuel; miscellaneous waste from Dutch research centres etc.; - lifetime of about 100 years; - compliance with the most recent radiological standards for operations; - consideration of external risks such as earthquake, aircraft crash, external explosion, flooding, tornado. A major feature of the facility is that cooling of the stored high heat generating waste is totally passive by natural air convection. Once unloaded from the shipping casks the waste packages are checked and emplaced in bunkers if they do not generate significant heat and in vertical wells if they generate heat, like vitrified waste and fuel. Spent fuel is canistered before being stored. HABOG has been designed (i) by SGN for the basic concept, relying on experience from similar installations in France, at La Hague and Cadarache, particularly for the natural convection cooling system of the storage wells; (ii) by COVRA for some specific aspects, e.g. criticality safety; and (iii) by HBKC (Dutch civil engineering contractor) for civil engineering, particularly the consideration of seism, aircraft crash and flooding. The concept has been approved by Dutch Safety Authorities. Construction is under SGN' responsibility, except civil works entrusted to HBKC. The manufacturing of the main equipment is under progress as well as the construction works on site. The HABOG facility will start receiving packages in 2003. (authors)

  11. Industrial gamma irradiation facility with a wet storage source in Syrian Arab Republic

    International Nuclear Information System (INIS)

    A gamma radiation facility was built in Damascus, Syria. The plant (ROBO) is a Co-60 wet storage, batch/continuous facility with nominal capacity of 1.85x1016Bq. The initial activity is 3.7x1015Bq. The ratio of maximum absorbed dose to the minimum one within irradiated materials is around 1.3+/-0.03. The irradiator consists of two sections to select required sources for irradiation. Two pools were constructed. The main pool will serve as biological shield for the main sources frame. The second pool will host a fixed circular frame to be used as calibration source or to irradiate small samples to low doses. The conveyor consists of a chain facility moving along trucks. A repair section is provided on the conveyor route in the load-unload area for carrying out inspection, repair, etc. The trucks are holed with a rectangular frames. Loading, unloading and rearrangement of the products is carried out automatically. This mechanism is carried out by seven pneumatic cylinders, lifting devices and roller conveyors. Many safety features were included: push-back platform, followed by pit used as a physical barrier. Interlocks are connected to the platform, pit cover and to ionization chambers. In case of power failure or any overriding of interlocks, the irradiator comes to emergency dropping. Ventilation system, fire system, emergency power and closed water purification system are indicated on control panel. The facility will be utilized for medical products sterilization, research and calibration

  12. Evaluation of closure alternatives for the Building 3001 Storage Canal at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The Bldg. 3001 Storage Canal at ORNL is leaking approximately 400 gal of water per day. This report presents the Bechtel National Inc. (BNI) Team's evaluation of plans and presents recommendations for interim closure alternatives to stop the release of radionuclides and potential release of heavy metals into the environment. This is a conceptual evaluation and does not include detailed engineering of physical mitigation methods. The alternatives address only interim closure measures and not final decommissioning of the canal

  13. Radioactive waste storage at the CEA Centre in Cadarache; transfer from the -storage yard- to the CEDRA facility: an illustration of changes in the safety requirements

    International Nuclear Information System (INIS)

    A lot of changes have been made to the nuclear waste storage and disposal strategy over the last few years thanks to technological progress and changes in the requirements applicable in the sector. In this article, the authors present a concrete example of the actions undertaken, at the request of the French Nuclear Safety Authority (ASN), by the CEA Centre at Cadarache, regarding the Cadarache Centre waste storage facility (BNI 56), a facility which was originally intended as a permanent repository for solid waste. Commissioned in 1969, BNI 56 is made up of various trenches and pits which no longer meet current ASN requirements. To clean up these trenches, a legacy from the past, now requires considerable resources and involves many problems, especially due to uncertainty surrounding the nature, activity levels, packaging and volume of this waste. ASN ensures that the CEA will fully assume its overriding responsibility in the matter and implement safe, rigorous and transparent management solutions for all the waste. The BNI 56 trenches are an ongoing and concrete example of the difficulties inherent in recovering waste from storage and dismantling former facilities the design of which failed to take such aspects into account. This waste is now being repackaged so that it can be stored at a new basic nuclear installation called CEDRA (packaging and storage of radioactive waste) which complies with the safety requirements currently in force. This facility, commissioned in 2006, is intended for the storage of Type B solid radioactive waste for a period of 50 years pending construction of a deep geological repository or long-term storage facility. (authors)

  14. Assessment of Energy Storage Alternatives in the Puget Sound Energy System Volume 2: Energy Storage Evaluation Tool

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Di; Jin, Chunlian; Balducci, Patrick J.; Kintner-Meyer, Michael CW

    2013-12-01

    This volume presents the battery storage evaluation tool developed at Pacific Northwest National Laboratory (PNNL), which is used to evaluate benefits of battery storage for multiple grid applications, including energy arbitrage, balancing service, capacity value, distribution system equipment deferral, and outage mitigation. This tool is based on the optimal control strategies to capture multiple services from a single energy storage device. In this control strategy, at each hour, a look-ahead optimization is first formulated and solved to determine battery base operating point. The minute by minute simulation is then performed to simulate the actual battery operation. This volume provide background and manual for this evaluation tool.

  15. Containers for short-term storage of nuclear materials at the Los Alamos plutonium facility

    International Nuclear Information System (INIS)

    The Los Alamos Plutonium Facility for the past 18 yr has stored nuclear samples for archiving and in support of nuclear materials research and processing programs. In the past several years, a small number of storage containers have been found in a deteriorated condition. A failed plutonium container can cause personnel contamination exposure and expensive physical area decontamination. Containers are stored in a physically secure radiation area vault, making close inspection costly in the form of personnel radiation exposure and work time. A moderate number of these containers are used in support of plutonium processing and must withstand daily handling abuse. A 2-yr evaluation of failed containers and those that have shown no deterioration has been conducted. Based on that study, a program was established to formalize our packing methods and materials and standardize the size and shape of containers that are used for short-term use. A standardized set of containers was designed, evaluated, tested, and procured for use in the facility. This paper reviews our vault storage problems, shows some failed containers, and presents our planned solutions to provide safe and secure containment of nuclear materials

  16. Stress evaluation of the primary tank of a double-shell underground storage tank facility

    International Nuclear Information System (INIS)

    A facility called the Multi-Function Waste Tank Facility (MWTF) is being designed at the Department of Energy's Hanford site. The MWTF is expected to be completed in 1998 and will consist of six underground double-shell waste storage tanks and associated systems. These tanks will provide safe and environmentally acceptable storage capacity to handle waste generated during single-shell and double-shell tank safety mitigation and remediation activities. This paper summarizes the analysis and qualification of the primary tank structure of the MWTF, as performed by ICF Kaiser Hanford during the latter phase of Title 1 (Preliminary) design. Both computer finite element analysis (FEA) and hand calculations methods based on the so-called Tank Seismic Experts Panel (TSEP) Guidelines were used to perform the analysis and evaluation. Based on the evaluations summarized in this paper, it is concluded that the primary tank structure of the MWTF satisfies the project design requirements. In addition, the hand calculations performed using the methodologies provided in the TSEP Guidelines demonstrate that, except for slosh height, the capacities exceed the demand. The design accounts for the adverse effect of the excessive slosh height demand, i.e., inadequate freeboard, by increasing the hydrodynamic wall and roof pressures appropriately, and designing the tank for such increased pressures

  17. HEU to LEU conversion and blending facility: Metal blending alternative to produce LEU oxide for disposal

    International Nuclear Information System (INIS)

    US DOE is examining options for disposing of surplus weapons-usable fissile materials and storage of all weapons-usable fissile materials. The nuclear material is converted to a form more proliferation- resistant than the original form. Blending HEU (highly enriched uranium) with less-enriched uranium to form LEU has been proposed as a disposition option. Five technologies are being assessed for blending HEU. This document provides data to be used in environmental impact analysis for the HEU-LEU disposition option that uses metal blending with an oxide waste product. It is divided into: mission and assumptions, conversion and blending facility descriptions, process descriptions and requirements, resource needs, employment needs, waste and emissions from plant, hazards discussion, and intersite transportation

  18. Commissioning of the DESIREE storage rings – a new facility for cold ion-ion collisions

    International Nuclear Information System (INIS)

    We report on the ongoing commissioning of the Double ElectroStatic Ion Ring ExpEriment, DESIREE, at Stockholm University. Beams of atomic carbon anions (C−) and smaller carbon anion molecules (C−2, C−3, C−4 etc.) have been produced in a sputter ion source, accelerated to 10 keV or 20 keV, and stored successfully in the two electrostatic rings. The rings are enclosed in a common vacuum chamber cooled to below 13 Kelvin. The DESIREE facility allows for studies of internally relaxed single isolated atomic, molecular and cluster ions and for collision experiments between cat- and anions down to very low center-of-mass collision energies (meV scale). The total thermal load of the vacuum chamber at this temperature is measured to be 32 W. The decay rates of stored ion beams have two components: a non-exponential component caused by the space charge of the beam itself which dominates at early times and an exponential term from the neutralization of the beam in collisions with residual gas at later times. The residual gas limited storage lifetime of carbon anions in the symmetric ring is over seven minutes while the 1/e lifetime in the asymmetric ring is measured to be about 30 seconds. Although we aim to improve the storage in the second ring, the number of stored ions are now sufficient for many merged beams experiments with positive and negative ions requiring milliseconds to seconds ion storage

  19. Facile synthesis of porous NiO hollow microspheres and its electrochemical lithium-storage performance

    International Nuclear Information System (INIS)

    Highlights: ► Porous NiO hollow microspheres are fabricated. ► Each microsphere consists of many nanoparticles of 30–80 nm. ► The synthesis involves an ultrasound-assisted route followed by thermal annealing. ► The microspheres show enhanced lithium-storage performance due to porous architecture. -- Abstract: Novel porous NiO hollow microspheres are fabricated by a facile two-step method involving the ultrasound-assisted synthesis of nickel oxalate precursors and subsequent thermal annealing in air. The as-prepared NiO microspheres are composed of loosely packed nanoparticles with diameters around 30–80 nm, and have a main pore distribution from 3 to 20 nm with a mean pore size of 5.7 nm. When evaluated as anode material for lithium ion battery, the porous NiO hollow microspheres showed enhanced electrochemical performance with high lithium storage capacity, satisfactory cyclability and rate capacity. The reversible capacity of the NiO microspheres retained 380 mAh g−1 after 30 cycles at 200 mA g−1. Even when cycled at various rate for more than 60 cycles, the capacity could recover to 520 mAh g−1 for the current of 100 mA g−1. The good lithium-storage performance can be attributed to the unique porous architecture, which provides the structural flexibility for volume change and the routes for fast Li+ diffusion

  20. Determination of uranium distribution coefficient at Thabana storage facility using in-situ techniques

    International Nuclear Information System (INIS)

    Full text of publication follows: Distribution coefficients (Kd) to a large extent determine the suitability of a site to host a radioactive waste repository. Determining Kd values is not a simple exercise mainly because of its dependence on a number of factors. By applying the in-situ technique, which is discussed in this paper, the Kd value of uranium at the storage site was determined. This approach avoids the crushing or disturbing in any way the soil or rock samples, minimising the uncertainties in the final outcome. The intervention exercise at Thabana Storage Facility provided an opportunity of determining the distribution coefficient of uranium under site-specific conditions. In an attempt to salvage a contaminated condenser and recover the enriched uranium in it, Trench 7 was excavated. The trench had been filled with radioactive waste as contaminated equipment or loose material; or packaged in metal drums and capped for approximately 5 years. According to nuclear regulations it constituted a nuclear incident and intervention was immediately instituted. The soil samples gouged out at various depths from the floor of the trench were analysed for uranium and other radionuclides. Soil samples were collected from 30 cm, 60 cm, 80 cm, 105 cm, 135 cm and 160 cm intervals below the trench floor. The paper presents an analytical model for uranium migration at Thabana Storage Facility that takes into account the site-specific features and processes, and its applicability is validated with field results. By fixing some parameters in the model, the distribution coefficient of uranium at the site is determined minimising the huge uncertainties often associated with the conventional techniques. The analysis results of both 238U and 235U are used for this purpose. The parametric sensitivity analysis of the mathematical model provided the uncertainty envelope of the distribution coefficient at the site. The computational results are compared to literature and laboratory

  1. Asphyxiation Incidents by Hydrogen Sulfide at Manure Storage Facilities of Swine Livestock Farms in Korea.

    Science.gov (United States)

    Park, Jihoon; Kang, Taesun; Jin, Suhyun; Heo, Yong; Kim, Kyungran; Lee, Kyungsuk; Tsai, Perngjy; Yoon, Chungsik

    2016-01-01

    Livestock workers are involved in a variety of tasks, such as caring for animals, maintaining the breeding facilities, cleaning, and manure handling, and are exposed to health and safety risks. Hydrogen sulfide is considered the most toxic by-product of the manure handling process at livestock facilities. Except for several reports in developed countries, the statistics and cause of asphyxiation incidents in farms have not been collected and reported systematically, although the number of these incidents is expected to increase in developing and underdeveloped countries. In this study, the authors compiled the cases of work-related asphyxiation incidents at livestock manure storage facilities and analyzed the main causes. In this survey, a total of 17 incidents were identified through newspapers or online searches and public reports. Thirty workers died and eight were injured due to work-related tasks and rescue attempts from 1998 to 2013 in Korea. Of the 30 fatalities, 18 occurred during manure handling/maintenance tasks and 12 during rescue attempts. All incidents except for one case occurred during the warm season from the late spring (April) to early autumn (September) when manure is likely to decompose rapidly. It is important to train employees involved in the operation of the facilities (i.e., owners, managers, employees) regarding the appropriate prevention strategies for confined space management, such as hazard identification before entry, periodical facility inspection, restriction of unnecessary access, proper ventilation, and health and safety. Sharing information or case reports on previous incidents could also help prevent similar cases from occurring and reduce the number of fatalities and injuries. PMID:26765950

  2. Experience gained with nuclear material accounting and control in storage facility for plutonium dioxide of SChK radiochemical plant

    International Nuclear Information System (INIS)

    The task for the computerized accounting of containers at the storage with barcoding equipment for inventory taking has been performed at achieve the pre-commissioning phase. This gave the following upgrade: decrease of the time spent by the personnel in storage compartments with plutonium dioxide during inventory taking, this diminishing the dose for personnel; changeover from traditional record book to computerized accounting of nuclear materials at the storage, which will make it possible to include the local workstation of the storage into computer network for nuclear material (NM) accounting at the Radiochemical plant; test and improve technique for the use of barcoding equipment for further introduction at plants and storage facilities of the SChK. Works are underway for further improvement of the NM accounting at the storage for plutonium dioxide

  3. Pilot scale facility to determine gaseous emissions from livestock slurry during storage.

    Science.gov (United States)

    Petersen, Søren O; Skov, Morten; Drøscher, Per; Adamsen, Anders P S

    2009-01-01

    Livestock production is a growing source of air pollution, locally and to the wider environment. Improved livestock manure management has the potential to reduce environmental impacts, but there is a need for methodologies to precisely quantify emissions. This paper describes and evaluates a novel storage facility for livestock slurry consisting of eight 6.5-m(3) cylindrical units. The stores may be equipped with airtight covers and ventilated during storage or during measurement only. Each store has eight air inlets (160 mm diameter) and a single outlet in the cover connected to a main ventilation duct. The stores can also be used as static enclosures. Ventilation can be regulated within the range of 50 to 250 m(3) h(-1). A gas sampling line enables sampling of odorants using automatic thermal desorption tubes, ammonia using acid traps, and greenhouse gases using gas sampling bags (pooled samples) or a syringe (time point samples). Complete recovery of CH(4) independent of ventilation rate was demonstrated. Vertical profiles of CO(2) and CH(4) above the slurry surface with and without ventilation and mixing of the headspace indicated methane oxidation activity in the surface crust. p-Cresol and 4-ethyl phenol emission from pig slurry was identified by GC-MS analysis of odor collected on adsorption tubes. Ammonia emissions between 0 and 166 mg N m(-2) h(-1) were observed during storage of pig slurry with and without surface crust and cover. A comparison of pooled and averaged time point measurements of CO(2), CH(4), and N(2)O indicated that pooled samples account for the diurnal variations under realistic storage conditions. PMID:19549932

  4. Partial Closure Report for the Area 514 Treatment and Storage Facility

    International Nuclear Information System (INIS)

    The purpose of this partial closure report is to inform the Department of Toxic Substances Control (DTSC) of the status of final closure of the Area 514 Treatment and Storage Facility (Area 514) and fulfill the DTSC requirements to proceed with the implementation of the interim action. Area 514 is located at the Livermore main site of Lawrence Livermore National Laboratory (LLNL). LLNL is owned by the U.S. Department of Energy (DOE) and operated jointly by DOE and the University of California. LLNL received its permit to operate hazardous waste facilities from DTSC in 1997. The hazardous waste treatment and storage operations of Area 514 were transferred to a newly constructed complex, the Decontamination and Waste Treatment Facility (DWTF), in 2003. Once the DWTF was operational, the final closure of Area 514 began in accordance with the DTSC-approved closure plan in June 2004. Abri Environmental Engineering, Inc., was retained by LLNL to observe the A514 closure process and prepare this partial closure report and certification. Prior to closure, the configuration of the Area 514 Treatment and Storage Facility consisted of Building 514, the Area 514-1 Container Storage and Treatment unit, the Area 514-2 Container Storage Unit (CSU), the Area 514-3 CSU, Building 513, the Wastewater Treatment Tank Farm unit, and the associated Area 514 yard area. The fenced area of Area 514 included approximately 27,350 ft2 on the LLNL Livermore site. To date, except for the 514-3 CSU, all of the other Area 514 structures have been demolished; and sampling and analysis have taken place. The non-hazardous wastes have been disposed of. At the time of writing this report, the hazardous, mixed, and low-level radioactive wastes are in the process of profiling for final disposition. Once the disposition of all wastes has been finalized, the implementation of the approved closure plan will be completed. As a part of the closure process, LLNL is required to submit a closure report and a

  5. Partial Closure Report for the Area 514 Treatment and Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Abri, M

    2005-05-02

    The purpose of this partial closure report is to inform the Department of Toxic Substances Control (DTSC) of the status of final closure of the Area 514 Treatment and Storage Facility (Area 514) and fulfill the DTSC requirements to proceed with the implementation of the interim action. Area 514 is located at the Livermore main site of Lawrence Livermore National Laboratory (LLNL). LLNL is owned by the U.S. Department of Energy (DOE) and operated jointly by DOE and the University of California. LLNL received its permit to operate hazardous waste facilities from DTSC in 1997. The hazardous waste treatment and storage operations of Area 514 were transferred to a newly constructed complex, the Decontamination and Waste Treatment Facility (DWTF), in 2003. Once the DWTF was operational, the final closure of Area 514 began in accordance with the DTSC-approved closure plan in June 2004. Abri Environmental Engineering, Inc., was retained by LLNL to observe the A514 closure process and prepare this partial closure report and certification. Prior to closure, the configuration of the Area 514 Treatment and Storage Facility consisted of Building 514, the Area 514-1 Container Storage and Treatment unit, the Area 514-2 Container Storage Unit (CSU), the Area 514-3 CSU, Building 513, the Wastewater Treatment Tank Farm unit, and the associated Area 514 yard area. The fenced area of Area 514 included approximately 27,350 ft2 on the LLNL Livermore site. To date, except for the 514-3 CSU, all of the other Area 514 structures have been demolished; and sampling and analysis have taken place. The non-hazardous wastes have been disposed of. At the time of writing this report, the hazardous, mixed, and low-level radioactive wastes are in the process of profiling for final disposition. Once the disposition of all wastes has been finalized, the implementation of the approved closure plan will be completed. As a part of the closure process, LLNL is required to submit a closure report and a

  6. Radiological safety assessment for a low-level radioactive solid waste storage facility: preliminary risk evaluation by reliability techniques

    International Nuclear Information System (INIS)

    The applicability of reliability techniques was examined to the determination of quantitative risks presented by a low-level radioactive solid waste storage facility. Fault trees and event trees were defined based on many relevant assumptions to obtain the average occurrence rate of rare accidents which could lead to potential hazards to the general public. The amount of radioactivity which would be transported into the environment from a storage facility was calculated using assumptions and/or estimates of the magnitude of each accident, together with estimates of probability of occurrence, and was used as an index for measuring the potential risks. Some valuable results were obtained in this study under the limits considered. These are as follows: (1) Reliability techniques are effective and promising for assessing the quantitative risks due to storing radioactive wastes in a waste package storage facility for long periods; (2) The main failures associated with an accident are summarized and listed; (3) The advantages and disadvantages of two types of waste package storage room and the amounts of radioactivity which would be released accidentally from them are also summarized and listed; and (4) The improvements to a storage facility that are desirable from a radiological safety aspect are proposed. (author)

  7. Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility

    International Nuclear Information System (INIS)

    The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable

  8. Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, D.J.; Brehm, J.R.

    1994-01-01

    The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable.

  9. Advice about the safety of graphite storage silos of Saint Laurent des Eaux facility

    International Nuclear Information System (INIS)

    This document is the safety analysis made by the national association of the local commissions of information about nuclear activities (ANCLI), about the safety of graphite storage silos of Saint Laurent des Eaux nuclear facility. The analysis covers: the operation safety and the accident hypothesis, the monitoring of indoor and outdoor contamination in routine situation, the geotechnical characteristics of the site environment, the isotopic inventory and the estimation of radioactivity in routine and accidental situation, the estimation of doses received by the population in accidental situation and the internal emergency plan. After examination of these different points, the scientific committee of the ANCLI considers that a new global evaluation of risks, which integrates more recent exposure data, has to be carried out. (J.S.)

  10. Management Programme for Research Reactor Spent Nuclear Fuel Storage and Interim Storage Facilities at Nuclear Research Institute Rez Plc, Czech Republic

    International Nuclear Information System (INIS)

    LVR-15 is a research reactor that operates in NRI Rez plc, Czech Republic since 1957. From the first criticality of the reactor until 2007, more than 600 fuel assemblies have been used in the reactor core, resulting in a large quantity of spent fuel. This paper describes the management of Research Reactor Spent Nuclear Fuel (RRSNF) storage at NRI Rez plc. Characteristics of fuel types used (EK-10, IRT-2M 80% enriched and IRT-2M 36% enriched), and characteristics of interim storage facilities and infrastructure available are described. The paper emphasizes the experience gained during the preparatory works for the SNF shipment (facility and equipment modification, cask licenses) and the preparation of the SNF for transport, in particular its checking, repackaging in a hot cell, loading into the VPVR/M casks, drying, manipulation, completion of the transport documentation, etc. including its transport to the High Level Waste Storage facility before its transportation to the Russian Federation. Future Russian Federation options for the spent fuel management at NRI Rez plc, including possibility of additional shipments to the Russian Federation, or interim storage in SKODA VPVR/M cask systems at NRI Rez is also discussed. (author)

  11. Development of a methodology to accelerate a spontaneous grass colonization in a tailings storage facility under semiarid mediterranean climate type

    Science.gov (United States)

    Ginocchio, Rosanna; Arellano, Eduardo; Morales-Ladron de Guevara, Arturo

    2016-04-01

    Phytostabilization of massive mine tailings (>400 he) under semiarid environments is challenging, particularly when no organic amendments are locally available and no irrigation is possible. Increasing tendency for reprocessing old tailings to recover valued metals further pioneer the need for simple but effective plant covers. The choice of plant species and form of management are thus very important. CODELCO-Chile chose the Cauquenes post-operational tailings storage facility (TFS; 700 ha), that will be reprocessed for copper and other elements in the near future, to evaluate efficacy of the phytostabilization technology under semiarid conditions in central Chile. Surface application of a polymer (Soiltac TM) has been used for wind control of tailings but phytostabilization is considered as a best cost-effective alternative. A field study was performed to define a management program to improve the establishment and cover of an annual native grass (Vulpia myuros var. megalura), a spontaneous colonizer of the TSF. Considered management factors were control of macro herbivores (with and without fence), macronutrient improvement (with and without application of N-rich foliar fertilizer), and improvement of seed retention in the substrate (with and without small-scale rugosity; with and without lived wind-breakers; with and without mechanical wind-breakers). Each treatment was replicated three times and established in 2 m x 2 m quadrats. Plant response variables were monitored after 1 and 2 grass growing seasons. Application of N-rich foliar fertilizer and any wind control mechanism for seed retention in the substrate were effective for significantly improving both grass cover and biomass production in time, irrespective of macro-herbivore control. Seed production was significantly improved when macro herbivores were excluded and was positively and significantly correlated to vegetative biomass production. When applying this management program for tailings

  12. Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2

    International Nuclear Information System (INIS)

    This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2

  13. Facile Synthesis of Porous ZnMnO3 Spherulites with a High Lithium Storage Capability

    International Nuclear Information System (INIS)

    Graphical abstract: Porous ZnMnO3 spherulites show an enhanced high lithium storage capability when potentially applied as a lithium-ion battery anode for the first time. - Highlights: • Composite Zn0.5Mn0.5CO3 microspheres are facilely co-precipitated. • Porous ZnMnO3 spherulites can be used as a lithium-ion battery anode. • Porous ZnMnO3 spherulites show superior electrochemical properties. • A synergistic effect of Zn-O and Mn-O components in cubic ZnMnO3 is proposed. - Abstract: In this paper, pure-phase ZnMnO3 porous spherulites are uniquely synthesized through the thermal decomposition of Zn-Mn binary carbonate precursors facilely co-precipitated at room temperature, possessing an average diameter of 1.2 ± 0.3 μm and acquiring porosity with a specific surface area of 24.3 m2 g−1. When tentatively applied as lithium-ion battery anodes for the first time, these porous spherulites deliver an initial discharge capacity of 1294 mAh g−1 at 500 mA g−1 and retain an reversible value of 879 mAh g−1 over 150 cycles. By comparison, the equimolar powder mixture of nano-sized ZnO and MnO2 synergistically shows a higher lithium storage capability than the two unary transition metal oxides, but lower than anode material ZnMnO3. Aside from its nanostructured characteristics, an inner atomic synergistic effect within the cubic lattices may account for the superior electrochemical performance of well-crystallized ZnMnO3

  14. Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

    Energy Technology Data Exchange (ETDEWEB)

    Moore, L.; Shanteau, C.

    1992-12-01

    This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county's future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

  15. Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

    Energy Technology Data Exchange (ETDEWEB)

    Moore, L.; Shanteau, C.

    1992-12-01

    This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county`s future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

  16. Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

    International Nuclear Information System (INIS)

    This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county's future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County

  17. Radioprotection considerations on the expansion project of an interim storage facility for radioactive waste

    International Nuclear Information System (INIS)

    The Radioactive Waste Management (GRR) of the Nuclear and Energy Research Institute (IPEN/CNEN-SP) receives, treats, packs, characterizes and stores institutional radioactive wastes generated at IPEN-CNEN/SP and also those received from several radiological facilities in the country. The current storage areas have been used to store the treated radioactive waste since the early 1980's and their occupation is close to their full capacity, so a storage area expansion is needed. The expansion project includes the rebuilding of two sheds and the enlargement of the third one in the area currently occupied by the GRR and in a small adjacent area. The civil works will be in controlled area, where the waste management operations will be maintained, so all the steps of this project should be planned and optimized, from the radioprotection point of view. The civil construction will be made in steps. During the project implementation there will be transfer operations of radioactive waste packages to the rebuilt area. After these transfer operations, the civil works will proceed in the vacant areas. This project implies on radiological monitoring, dose control of the involved workers, decontamination and clearance of areas and it is also envisaged the need for repacking of some radioactive waste. The objective this paper is to describe the radioprotection study developed to this expansion project, taking into account the national radioprotection and civil construction regulations. (author)

  18. A Facile Route to Metal Oxides/Single-Walled Carbon Nanotube Macrofilm Nanocomposites for Energy Storage

    Directory of Open Access Journals (Sweden)

    Zeyuan eCao

    2015-05-01

    Full Text Available Nanocomposites consisting of transition-metal oxides and carbon nanomaterials with a desired size and structure are highly demanded for high performance energy storage devices. Here, a facile two-step and cost-efficient approach relying on directly thermal treatment of chemical-vapor-deposition products is developed as a general synthetic method to prepare a family of metal oxides (MxOy (M=Fe, Co, Ni/single-walled carbon nanotube (SWNT macrofilm nanocomposites. The MxOy nanoparticles obtained are of 3-17 nm in diameter and homogeneously anchor on the free-standing SWNT macrofilms. NiO/SWNT also exhibits a high specific capacitance of 400 F g-1 and fast charge-transfer Faradaic redox reactions to achieve asymmetric supercapacitors with a high power and energy density. All MxOy/SWNT nanocomposites could deliver a high capacity beyond 1000 mAh g-1 and show excellent cycling stability for lithium-ion batteries. The impressive results demonstrate the promise for energy storage devices and the general approach may pave the way to synthesize other functional nanocomposites.

  19. Vibro Replacement, Dynamic Compaction, and Vibro Compaction case histories for petroleum storage tank facilities

    Energy Technology Data Exchange (ETDEWEB)

    Beaton, N; Scott, J. [Geopac West Ltd., Richmond, BC (Canada)

    2010-07-01

    This paper discussed approaches to tank farm ground improvement via 3 Canadian ground improvement case histories in order to set forth the advantages of ground improvement for foundation support at petroleum storage tank facilities. Each case study featured a particular set of site conditions, performance criteria, and ground improvement techniques selected to attain the desired foundation performance. The first case study involved a Vibro Replacement stone column to meet strict seismicity requirements, the second employed Dynamic Compaction to mitigate deep variable fill within a former gravel pit, and the last encompassed Vibro Compaction applied to a site with a sand fill soil profile. The site conditions, the design requirements, the ground improvement solution, the execution, and the quality control techniques and results were presented for each case history. Soil reinforcement and ground improvement to treat loose and soft soils below heavy storage tanks can be an economical solution to foundation design challenges. However, it is important to select proper methods and tailor the densification programs to the specific subsoil conditions and design requirements. In each application, the selected ground improvement technique exceeded the specified in-situ testing requirements. 3 refs., 9 figs.

  20. PU/SS Eutectic Assessment In 9975 Packagings In A Storage Facility During Extended Fire

    International Nuclear Information System (INIS)

    In a radioactive material (RAM) packaging, the formation of eutectic at the Pu/SS (plutonium/stainless steel) interface is a serious concern and must be avoided to prevent of leakage of fissile material to the environment. The eutectic temperature for the Pu/SS is rather low (410 C) and could seriously impact the structural integrity of the containment vessel under accident conditions involving fire. The 9975 packaging is used for long term storage of Pu bearing materials in the DOE complex where the Pu comes in contact with the stainless steel containment vessel. Due to the serious consequences of the containment breach at the eutectic site, the Pu/SS interface temperature is kept well below the eutectic formation temperature of 410 C. This paper discusses the thermal models and the results for the extended fire conditions (1500 F for 86 minutes) that exist in a long term storage facility and concludes that the 9975 packaging Pu/SS interface temperature is well below the eutectic temperature.

  1. Safety issues in construction of facilities for long-term storage of radioactive waste at vector site

    International Nuclear Information System (INIS)

    In Ukraine, it is planned to create a number of near-surface facilities for disposal of short-lived RW and long-term (up to 100 years) storage of long-lived RW at the Vector site in the Chernobyl exclusion zone. The expected streams of long-lived RW are analyzed in the paper. According to the analysis of RW streams, in particular, issues are considered on development of RW acceptance criteria, admissible radiological impacts during preparation of RW for long-term storage, reliability of barriers (RW packages, modules and structures, etc.) during long-term storage of RW. (orig.)

  2. Environmental assessment for the Strategic Petroleum Reserve Big Hill facility storage of commercial crude oil project, Jefferson County, Texas

    International Nuclear Information System (INIS)

    The Big Hill SPR facility located in Jefferson County, Texas has been a permitted operating crude oil storage site since 1986 with benign environmental impacts. However, Congress has not authorized crude oil purchases for the SPR since 1990, and six storage caverns at Big Hill are underutilized with 70 million barrels of available storage capacity. On February 17, 1999, the Secretary of Energy offered the 70 million barrels of available storage at Big Hill for commercial use. Interested commercial users would enter into storage contracts with DOE, and DOE would receive crude oil in lieu of dollars as rental fees. The site could potentially began to receive commercial oil in May 1999. This Environmental Assessment identified environmental changes that potentially would affect water usage, power usage, and air emissions. However, as the assessment indicates, changes would not occur to a major degree affecting the environment and no long-term short-term, cumulative or irreversible impacts have been identified

  3. Final Safety Report for Central Interim Storage Facility for Radioactive Waste from Small Producers in Brinje near Ljubljana

    International Nuclear Information System (INIS)

    In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage for radioactive waste from small producers in Brinje. At the same time in accordance with a Decree on the Mode, Subject and Terms of Performing the Public Service of Radioactive Waste Management (Official Gazette of RS, 32/99) the ARAO agency was appointed to perform the public service of radioactive waste management for waste produced in Slovenia in industry, medicine and research. After taking over responsibility for the storage the ARAO thoroughly reviewed the facility and the stored inventory. Based on the findings of this review the ARAO agency prepared a basic document for the facility i.e. Final Safety Report for the Central Interim Storage for radioactive waste from small producers in Brinje. The safety report is based on the present state of the facility, its location, stored inventory and present operation. The latter is limited to storing of already stored waste, acceptance of new waste only in emergency cases, and internal transport of the accepted waste with a forklift or manually. The Final Safety Report is prepared in accordance with the requirements of Regulation E2 and deals with the following areas: The safety approach to LILW storage, Description and location analysis of the Central interim storage, Technical features of the Central interim storage, Safety analysis of the Central interim storage, Organisational measures for normal operation of the Central interim storage, Operational conditions and limitations, Ionising radiation protection service, its methods and equipment, Radioactive waste management and disposal, Review of the plans, measures and procedures to prevent radiological accidents, Quality assurance programme, Review of the measures for physical protection of the LILW storage and stored radioactive waste, Planned measures and necessary equipment for the closure of the Central interim storage. Safety analysis proves that the facility

  4. Inspection experience with RA-3 spent nuclear fuel assemblies at CNEA's central storage facility

    International Nuclear Information System (INIS)

    Aluminum-based spent nuclear fuel from Argentina's RA-3 research reactor is to be shipped to the Savannah River Site near Aiken, South Carolina, USA. The spent nuclear fuel contains highly enriched uranium of U.S. origin and is being returned under the US Department of Energy's Foreign Research Reactor/Domestic Research Reactor (FRR/DRR) Receipt Program. An intensive inspection of 207 stored fuel assemblies was conducted to assess shipping cask containment limitations and assembly handling considerations. The inspection was performed with video equipment designed for remote operation, high portability, easy setup and usage. Fuel assemblies were raised from their vertical storage tubes, inspected by remote video, and then returned to their original storage tube or transferred to an alternate location. The inspections were made with three simultaneous video systems, each with dedicated viewing, digital recording, and tele-operated control from a shielded location. All 207 fuel assemblies were safely and successfully inspected in fifteen working days. Total dose to personnel was about one-half of anticipated dose. (author)

  5. ISABELLE: A Proposal for Construction of a Proton--Proton Storage Accelerator Facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-05-01

    The construction of an Intersecting Storage Accelerator Facility (ISA or ISABELLE) at Brookhaven National Laboratory is proposed. ISABELLE will permit the exploration of proton-proton collisions at center-of-mass energies continuously variable from 60 to 400 GeV and with luminosities of 1032 to 1033 cm-2 sec-1 over the entire range. An overview of the physics potential of this machine is given, covering the production of charged and neutral intermediate vector bosons, the hadron production at high transverse momentum, searches for new, massive particles, and the energy dependence of the strong interactions. The facility consists of two interlaced rings of superconducting magnets in a common tunnel about 3 km in circumference. The proton beams will collide at eight intersection regions where particle detectors will be arranged for studying the collision processes. Protons of approximately 30 GeV from the AGS will be accumulated to obtain the design current of 10A prior to acceleration to final energy. The design and performance of existing full-size superconducting dipoles and quadrupoles is described. The conceptual design of the accelerator systems and the conventional structures and buildings is presented. A preliminary cost estimate and construction schedule are given. Possible future options such as proton-antiproton, proton-deuteron and electron-proton collisions are discussed.

  6. Radiation shielding and dose rate evaluation at the interim storage facility for spent fuel from Cernavoda NPP

    International Nuclear Information System (INIS)

    At present studies necessary to license the Interim Storage Facility for the Spent Fuel (CANDU type) from Cernavoda NPP are developed in our country.The spent fuel from Cernavoda NPP is discharged into Spent Fuel Bay in Service Building of the plant, where it remains several years for cooling. After this period, the bundles of spent fuel are to be transferred to the Interim Storage Facility.The dry interim storage solution seems to be the most appropriate variant for Cernavoda NPP.The design of the Spent Fuel Interim Storage Facility must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility achievement. In this paper we intend to present the calculation of radiation shielding at the spent fuel interim storage facility for two technical solutions: - Concrete Monolithic Module and Concrete Storage Cask. In order to quantify the fuel composition after irradiation, the isotope generation and depletion code ORIGEN 2.1 has been used, taking into account a cooling time of 7 years and 9 years, respectively, for these two variants. The shielding calculations have been performed using the computer codes QAD-5K and MICROSHIELD-4. The evaluations refer only to gamma radiation because the resulting neutron source (from (α,n) reactions and spontaneous fission) is insignificant as compared to the gamma source. The final results consist in the minimum thickness of the shielding and the corresponding external dose rates, ensuring a design average dose rate based on national and international regulations. (authors)

  7. Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities; Instalaciones de almacenamiento de combustible nuclear gastado en seco para instalaciones nucleares mexicanas

    Energy Technology Data Exchange (ETDEWEB)

    Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

  8. MONITOR: A computer model for estimating the costs of an integral monitored retrievable storage facility

    International Nuclear Information System (INIS)

    The MONITOR model is a FORTRAN 77 based computer code that provides parametric life-cycle cost estimates for a monitored retrievable storage (MRS) facility. MONITOR is very flexible in that it can estimate the costs of an MRS facility operating under almost any conceivable nuclear waste logistics scenario. The model can also accommodate input data of varying degrees of complexity and detail (ranging from very simple to more complex) which makes it ideal for use in the MRS program, where new designs and new cost data are frequently offered for consideration. MONITOR can be run as an independent program, or it can be interfaced with the Waste System Transportation and Economic Simulation (WASTES) model, a program that simulates the movement of waste through a complete nuclear waste disposal system. The WASTES model drives the MONITOR model by providing it with the annual quantities of waste that are received, stored, and shipped at the MRS facility. Three runs of MONITOR are documented in this report. Two of the runs are for Version 1 of the MONITOR code. A simulation which uses the costs developed by the Ralph M. Parsons Company in the 2A (backup) version of the MRS cost estimate. In one of these runs MONITOR was run as an independent model, and in the other run MONITOR was run using an input file generated by the WASTES model. The two runs correspond to identical cases, and the fact that they gave identical results verified that the code performed the same calculations in both modes of operation. The third run was made for Version 2 of the MONITOR code. A simulation which uses the costs developed by the Ralph M. Parsons Company in the 2B (integral) version of the MRS cost estimate. This run was made with MONITOR being run as an independent model. The results of several cases have been verified by hand calculations

  9. Integrated monitoring and reviewing systems for the Rokkasho Spent Fuel Receipt and Storage Facility

    International Nuclear Information System (INIS)

    The Rokkasho Spent Fuel Receipt and Storage (RSFS) Facility at the Rokkasho Reprocessing Plant (RRP) in Japan is expected to begin operations in 1998. Effective safeguarding by International Atomic Energy Agency (IAEA) and Japan Atomic Energy Bureau (JAEB) inspectors requires monitoring the time of transfer, direction of movement, and number of spent fuel assemblies transferred. At peak throughput, up to 1,000 spent fuel assemblies will be accepted by the facility in a 90-day period. In order for the safeguards inspector to efficiently review the resulting large amounts of inspection information, an unattended monitoring system was developed that integrates containment and surveillance (C/S) video with radiation monitors. This allows for an integrated review of the facility's radiation data, C/S video, and operator declaration data. This paper presents an outline of the integrated unattended monitoring hardware and associated data reviewing software. The hardware consists of a multicamera optical surveillance (MOS) system radiation monitoring gamma-ray and neutron detector (GRAND) electronics, and an intelligent local operating network (ILON). The ILON was used for time synchronization and MOS video triggers. The new software consists of a suite of tools, each one specific to a single data type: radiation data, surveillance video, and operator declarations. Each tool can be used in a stand-alone mode as a separate ion application or configured to communicate and match time-synchronized data with any of the other tools. A data summary and comparison application (Integrated Review System [IRS]) coordinates the use of all of the data-specific review tools under a single-user interface. It therefore automates and simplifies the importation of data and the data-specific analyses

  10. MONITOR: A computer model for estimating the costs of an integral monitored retrievable storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Reimus, P.W.; Sevigny, N.L.; Schutz, M.E.; Heller, R.A.

    1986-12-01

    The MONITOR model is a FORTRAN 77 based computer code that provides parametric life-cycle cost estimates for a monitored retrievable storage (MRS) facility. MONITOR is very flexible in that it can estimate the costs of an MRS facility operating under almost any conceivable nuclear waste logistics scenario. The model can also accommodate input data of varying degrees of complexity and detail (ranging from very simple to more complex) which makes it ideal for use in the MRS program, where new designs and new cost data are frequently offered for consideration. MONITOR can be run as an independent program, or it can be interfaced with the Waste System Transportation and Economic Simulation (WASTES) model, a program that simulates the movement of waste through a complete nuclear waste disposal system. The WASTES model drives the MONITOR model by providing it with the annual quantities of waste that are received, stored, and shipped at the MRS facility. Three runs of MONITOR are documented in this report. Two of the runs are for Version 1 of the MONITOR code. A simulation which uses the costs developed by the Ralph M. Parsons Company in the 2A (backup) version of the MRS cost estimate. In one of these runs MONITOR was run as an independent model, and in the other run MONITOR was run using an input file generated by the WASTES model. The two runs correspond to identical cases, and the fact that they gave identical results verified that the code performed the same calculations in both modes of operation. The third run was made for Version 2 of the MONITOR code. A simulation which uses the costs developed by the Ralph M. Parsons Company in the 2B (integral) version of the MRS cost estimate. This run was made with MONITOR being run as an independent model. The results of several cases have been verified by hand calculations.

  11. Conceptual design for an intermediate dry storage facility for Argentinean Atucha spent fuel

    International Nuclear Information System (INIS)

    Full text: The CNEA (Argentina National Atomic Energy Commission) is planning a new facility for the spent fuel of Atucha I according with the national policy to fulfill the requirement of the National Plan of Radioactive waste management with the lowest cost, having the flexibility to evaluate the fuel back end strategy in a wait and see approach. Spent fuel elements can be stored in concrete for many decades economically and safety as intermediate step, thereby providing adequate time to develop an integrated fuel disposal system, this provides flexibility from the fuel to decay, thus facilitating final disposal with decrease of the decay heat. A centralized storage for the NPP fuel elements (Embalse and Atucha I) with two very different fuel element and different enrichment was not considered, in order to minimize the radioactive waste movement. Nowadays the total life Atucha I spent fuels are in two wet pools, having fuel elements with 28 years old. For Embalse fuel elements type dry vertical concrete silos were successfully implemented for intermediate strategy. An intermediate storage for Atucha I was designed taking into account the following criteria: Assurance the fuel elements integrity for 30 years; Modular build-up to avoid over dimension systems; Low cost radiation shield (concrete and ground); Leak monitoring system for the containment integrity; Possibility to take out the failed containment; Enable the re-encapsulation and the reentry for the fuel containment; Minimize the auxiliary systems with high maintenance cost (passive); Compatible with the national regulatory commission (ARN) regulation with monitoring systems, similar with those implemented in our dry silos at Embalse; Transfer systems and hot cell facility near the pool storage to use its water treatment systems; Minimize secondary waste during wet pool to the intermediate storage. The Atucha I fuel element has 37 fuel rod in circular cluster geometry with an active length of 5,5 meters

  12. Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives

    International Nuclear Information System (INIS)

    This report has been prepared by the Department of Energy's Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration

  13. Calculation of radiation exposure of the environment of interim storage facilities for the dry storage of spent fuel in dual-purpose casks

    International Nuclear Information System (INIS)

    Acceptance problems in the public concerning the transport of spent nuclear fuel elements and a new political objective of the Federal Government have forced the German utilities to embark on on-site interim storage projects for the temporary storage of spent nuclear fuel elements. STEAG encotec GmbH, Essen, Germany, was awarded contracts for the conceptual planning including necessary shielding calculations for the majority of the 13 nuclear sites which opted for the dry storage concept. The capacity of the storage facilities ranges from 80 to 100 casks, according to the storage needs of the plants. The average dose rate at the surface of each cask was limited to 0.5 mSv/h, independent of the type of radiation. These new buildings should not significantly increase the exposure of the public to radiation already originating from the existing nuclear power plant. The layout of the storage building therefore has to ensure that additional target values of 10-20 Sv/y are not exceeded. These very low target values as well as the requirement to avoid high mechanical impacts to the casks in case of external events led to a thickness of walls and ceilings of between 1.2 m and 1.3 m. To remove the decay heat from the casks by natural convection sufficient cross sections of the air inlet and outlet ducts are required

  14. Optimal use of the Gaz de France underground gas storage facilities; Utilisation optimale des stockages souterrains de Gaz de France

    Energy Technology Data Exchange (ETDEWEB)

    Favret, F.; Rouyer, E.; Bayen, D.; Corgier, B. [Gaz de France (GDF), 75 - Paris (France)

    2000-07-01

    This paper describes the tools developed by Gaz de France to optimize the use of its whole set of underground gas storage facilities. After a short introduction about the context and the purposes, the methodology and the models are detailed. The operational results obtained during the last three years are presented, and some conclusions and perspectives are given. (authors)

  15. Drafting Recommendations for a Shared Statewide High-Density Storage Facility: Experiences with the State University Libraries of Florida Proposal

    Science.gov (United States)

    Walker, Ben

    2008-01-01

    In August 2007, an $11.2 million proposal for a shared statewide high-density storage facility was submitted to the Board of Governors, the governing body of the State University System in Florida. The project was subsequently approved at a slightly lower level and funding was delayed until 2010/2011. The experiences of coordinating data…

  16. Studies and research concerning BNFP: life of project operating expenses for away-from-reactor (AFR) spent fuel storage facility. Final report

    International Nuclear Information System (INIS)

    Life of Project operating expenses for a licensed Away-From-Reactor (AFR) Spent Fuel Storage Facility are developed in this report. A comprehensive business management structure is established and the functions and responsibilities for the facility organization are described. Contractual provisions for spent fuel storage services are evaluated

  17. Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ragaisis, Valdas; Poskas, Povilas; Simonis, Vytautas; Adomaitis, Jonas Erdvilas [Lithuanian Energy Institute, Kaunas (Lithuania). Nuclear Engineering Lab.

    2011-11-15

    New solid radioactive waste management and interim storage facilities will be constructed for the Ignalina Nuclear Power Plant to support ongoing decommissioning activities, including removal and treatment of operational waste from the existing storage buildings. The paper presents approach and methods that have been used to assess radiological impacts to the general public potentially arising under normal operation and accident conditions and to demonstrate compliance with regulations in force. The assessment of impacts from normal operation includes evaluation of exposure arising from release of airborne radioactive material and from facilities and packages containing radioactive material. In addition, radiological impacts from other nearby operating and planned nuclear facilities are taken into consideration. The assessment of impacts under accident conditions includes evaluation of exposure arising from the selected design and beyond design basis accidents. (orig.)

  18. Nanotubes within transition metal silicate hollow spheres: Facile preparation and superior lithium storage performances

    International Nuclear Information System (INIS)

    Highlights: • The hollow Co2SiO4, MnSiO3 and CuSiO3 were successfully prepared by a facile hydrothermal method using SiO2 nanosphere. • The hollow Co2SiO4, MnSiO3 and CuSiO3 were tested as anode materials for lithium batteries. • The hollow Co2SiO4, MnSiO3 and CuSiO3 delivered superior electrochemical performance. • The lithium storage mechanism is probe via cyclic voltammetry and XPS. - Abstract: A series of transition metal silicate hollow spheres, including cobalt silicate (Co2SiO4), manganese silicate (MnSiO3) and copper silicate (CuSiO3.2H2O, CuSiO3 as abbreviation in the text) were prepared via a simple and economic hydrothermal method by using silica spheres as chemical template. Time-dependent experiments confirmed that the resultants formed a novel type of hierarchical structure, hollow spheres assembled by numerous one-dimensional (1D) nanotubes building blocks. For the first time, the transition metal silicate hollow spheres were characterized as novel anode materials of Li-ion battery, which presented superior lithium storage capacities, cycle performance and rate performance. The 1D nanotubes assembly and hollow interior endow this kind of material facilitate fast lithium ion and electron transport and accommodate the big volume change during the conversion reactions. Our study shows that low-cost transition metal silicate with rationally designed nanostructures can be promising anode materials for high capacity lithium-ion battery

  19. Nanotubes within transition metal silicate hollow spheres: Facile preparation and superior lithium storage performances

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Fan; An, Yongling; Zhai, Wei; Gao, Xueping [Key Laboratory for Liquid–Solid Structural Evolution & Processing of Materials (Ministry of Education), Jinan 250100 (China); Feng, Jinkui, E-mail: jinkui@sdu.edu.cn [Key Laboratory for Liquid–Solid Structural Evolution & Processing of Materials (Ministry of Education), Jinan 250100 (China); Ci, Lijie [Key Laboratory for Liquid–Solid Structural Evolution & Processing of Materials (Ministry of Education), Jinan 250100 (China); Xiong, Shenglin [School of Materials Science and Engineering, School of Chemistry and Chemical Engineering, Shandong University, Jinan 250100 (China)

    2015-10-15

    Highlights: • The hollow Co{sub 2}SiO{sub 4}, MnSiO{sub 3} and CuSiO{sub 3} were successfully prepared by a facile hydrothermal method using SiO{sub 2} nanosphere. • The hollow Co{sub 2}SiO{sub 4}, MnSiO{sub 3} and CuSiO{sub 3} were tested as anode materials for lithium batteries. • The hollow Co{sub 2}SiO{sub 4}, MnSiO{sub 3} and CuSiO{sub 3} delivered superior electrochemical performance. • The lithium storage mechanism is probe via cyclic voltammetry and XPS. - Abstract: A series of transition metal silicate hollow spheres, including cobalt silicate (Co{sub 2}SiO{sub 4}), manganese silicate (MnSiO{sub 3}) and copper silicate (CuSiO{sub 3}.2H{sub 2}O, CuSiO{sub 3} as abbreviation in the text) were prepared via a simple and economic hydrothermal method by using silica spheres as chemical template. Time-dependent experiments confirmed that the resultants formed a novel type of hierarchical structure, hollow spheres assembled by numerous one-dimensional (1D) nanotubes building blocks. For the first time, the transition metal silicate hollow spheres were characterized as novel anode materials of Li-ion battery, which presented superior lithium storage capacities, cycle performance and rate performance. The 1D nanotubes assembly and hollow interior endow this kind of material facilitate fast lithium ion and electron transport and accommodate the big volume change during the conversion reactions. Our study shows that low-cost transition metal silicate with rationally designed nanostructures can be promising anode materials for high capacity lithium-ion battery.

  20. Friction stir welding - an alternative method for sealing nuclear waste storage canisters

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, R.E. [TWI Ltd, Cambridge (United Kingdom)

    2004-12-01

    When welding 50 mm thick copper a very high heat input is required to combat the high thermal diffusivity and only the Electron Beam Welding (EBW) process had this capability when this copper canister concept was conceived. Despite the encouraging results achieved using EBW with thick section copper, SKB felt that it would be prudent to assess other joining methods. This assessment concluded that friction welding, could also provide very high quality welds to satisfy the service life requirements of the SKB canister design. A friction welding variant called Friction Stir Welding (FSW) was shown to have the capability of welding 3 mm thick copper sheet with excellent integrity and reproducibility. This later provided sufficient encouragement for SKB to consider the potential of FSW as a method for joining thick section copper, using relatively simple machine tool based technology. It was thought that FSW might provide an alternative or complementary method for welding lids, or bases to canisters. In 1997 an FSW development programme started at TWI, focussed on the feasibility of welding 10 mm thick copper plate. Once this task was successfully completed, work continued to demonstrate that progressively thicker plate, up to 50 mm thick, could be joined. At this stage, with process viability established, a full size experimental FSW canister machine was designed and built. Work with this machine finished in January 2003, when it had been shown that FSW could definitely be used to weld lids to full size canisters. This report summarises the TWI development of FSW for SKB from 1997 to January 2003. It also highlights the important aspects of the process and the project milestones that will help to ensure that SKB has a welding technology that can be used with confidence for production fabrication of copper waste storage canisters in the future. The overall conclusion to this FSW development is that there is no doubt that the FSW process could be used to produce full

  1. Friction stir welding - an alternative method for sealing nuclear waste storage canisters

    International Nuclear Information System (INIS)

    When welding 50 mm thick copper a very high heat input is required to combat the high thermal diffusivity and only the Electron Beam Welding (EBW) process had this capability when this copper canister concept was conceived. Despite the encouraging results achieved using EBW with thick section copper, SKB felt that it would be prudent to assess other joining methods. This assessment concluded that friction welding, could also provide very high quality welds to satisfy the service life requirements of the SKB canister design. A friction welding variant called Friction Stir Welding (FSW) was shown to have the capability of welding 3 mm thick copper sheet with excellent integrity and reproducibility. This later provided sufficient encouragement for SKB to consider the potential of FSW as a method for joining thick section copper, using relatively simple machine tool based technology. It was thought that FSW might provide an alternative or complementary method for welding lids, or bases to canisters. In 1997 an FSW development programme started at TWI, focussed on the feasibility of welding 10 mm thick copper plate. Once this task was successfully completed, work continued to demonstrate that progressively thicker plate, up to 50 mm thick, could be joined. At this stage, with process viability established, a full size experimental FSW canister machine was designed and built. Work with this machine finished in January 2003, when it had been shown that FSW could definitely be used to weld lids to full size canisters. This report summarises the TWI development of FSW for SKB from 1997 to January 2003. It also highlights the important aspects of the process and the project milestones that will help to ensure that SKB has a welding technology that can be used with confidence for production fabrication of copper waste storage canisters in the future. The overall conclusion to this FSW development is that there is no doubt that the FSW process could be used to produce full

  2. TWTF design alternates

    International Nuclear Information System (INIS)

    The Transuranic Waste Treatment Facility (TWTF) will process transuranic (TRU) waste in retrievable storage at the Idaho National Engineering Laboratory (INEL). The costs for a TWTF concept using a slagging pyrolysis incinerator were excessive. Alternate concepts using a slow speed shredder, a rotary kiln incinerator, and concrete immobilization should result in significant cost reductions. These will be included in future TWTF considerations

  3. Circular letter from January 22, 2004 to the presidents of companies having the status of chartered storage facility

    International Nuclear Information System (INIS)

    This circular letter is intended for owners of storage facilities for petroleum products benefiting from the obligation of strategic storage according to the article 2 of law no 92-1443 from December 31, 1992. The attached document recalls the reasons and content of this obligation, the prevailing strategic storage rules in France (reference texts, products in concern, operators, stockpiles localization, product substitution possibilities..), the monthly declarations, the controls and sanctions, the annual plan of stocks localization, the obligation of information, the loss of chartered status or the renouncement. A schematic synthesis of the system of stockpiles constitution is presented in appendix, for France and for the French overseas departements. The other appendixes concern: the list of petroleum products concerned by the legal obligation of strategic storage, the relations between the professional committee of strategic stockpiles (CPSSP) and the anonymous society of security stocks management (SAGESS), and some examples of monthly and annual declaration forms. (J.S.)

  4. Facility for the storage of spent, heat-emitting and container-enclosed nuclear reactor fuel assemblies

    International Nuclear Information System (INIS)

    Patent for facility for the storage of spent, heat-emitting and container-enclosed nuclear reactor fuel assemblies, which are arranged within a building in a horizontal position and are cooled by a gas stream, whereby the building has a storage and a loading zone, characterized by the fact that pallet trucks arranged one above the other in a row and such that an interspace is left for the receiving positions for the containers, the the pallet trucks can be moved along rails that extend between two side walls arranged opposite to one another in the storage zone, that the storage zone can be loaded and unloaded by opening located in these two side walls, and that the gas stream only circulates within the building

  5. Study of nonneutral plasma storage in a magnetic trap with a rotating electric field at the lepta facility

    International Nuclear Information System (INIS)

    Results from experimental studies of plasma storage in a Penning-Malmberg trap at the LEPTA facility are presented. The number of stored particles is found to increase substantially when using the so-called “rotating wall” method, in which a transverse rotating electric field generated by a cylindrical segmented electrode cut into four pairs is applied to the plasma storage region. The conditions of transverse compression of the plasma bunch under the action of the rotating field and buffer gas are studied. The optimal storage parameters are determined for these experimental conditions. Mechanisms of the action of the rotating field and buffer gas on the process of plasma storage are discussed

  6. 75 FR 72679 - Renewable Energy Alternate Uses of Existing Facilities on the Outer Continental Shelf-Acquire a...

    Science.gov (United States)

    2010-11-26

    ... Federal Register on July 9, 2008 (73 FR 39376). The North American Industry Classification System (NAICS... Energy Alternate Uses of Existing Facilities on the Outer Continental Shelf--Acquire a Lease... an Outer Continental Shelf (OCS) renewable energy lease. We are taking this action because...

  7. 76 FR 8962 - Renewable Energy Alternate Uses of Existing Facilities on the Outer Continental Shelf-Acquire a...

    Science.gov (United States)

    2011-02-16

    ... published in the Federal Register on July 9, 2008 (73 FR 39376). The North American Industry Classification... Energy Alternate Uses of Existing Facilities on the Outer Continental Shelf--Acquire a Lease... acquisition of an Outer Continental Shelf (OCS) renewable energy lease. We are taking this action because...

  8. 76 FR 28178 - Renewable Energy Alternate Uses of Existing Facilities on the Outer Continental Shelf-Acquire a...

    Science.gov (United States)

    2011-05-16

    ... 9, 2008 (73 FR 39376). The North American Industry Classification System (NAICS) code for the... Energy Alternate Uses of Existing Facilities on the Outer Continental Shelf--Acquire a Lease... acquisition of an Outer Continental Shelf (OCS) renewable energy lease. We are taking this action...

  9. PEGASUS, a community project on the effects of gas in underground storage facilities for radioactive waste

    International Nuclear Information System (INIS)

    The paper describes the project PEGASUS, a project recently launched by the Commission of the European Communities, within the framework of its 4th five year (1990-1994) R and D programme on Management and Storage of Radioactive Waste, involving about 15 organisations and research institutes from at least seven Member States. The project covers studies of the processes of gas formation and possible gas release from the different waste types, ILW and HLW, under typical repository conditions in suitable geological formations as clay, salt and granite. Gas generation due to internal radiation in active cemented alpha waste packages and due to external radiation of samples of inactive cements and bitumen containing organic components will be investigated by CEA (F). Effects of microbiological degradation will be studied by CEA (F) and AEA (UK). In-situ and laboratory experiments on gas release from salt due to heat and radiolysis, carried out in the Asse salt mine (FRG) and in an irradiation facility at Saclay (F) have already given much data and more results will become available with the implementation of the HAW project. Gas transport through engineered barriers has been investigated by Taylor Woodrow (UK), on clay barriers and by AEA (UK) on concrete barriers. In Germany (DBE, GSF et al.) experimental studies are starting on gas transport through salt bricks used as components for dams in galleries. Moreover, a study has started on appropriate sealing of HLW emplacement holes. Gas migration through geological formations, in particular clay and salt, will be investigated by SCK/CEN (B) and ANDRA (F). The research on clay includes laboratory testing on Boom clay samples, as well as in-situ gas injection experiments in the underground facility at Mol. Regarding salt, experiments will be carried out in the potash mine in Alsace (F). Most of these experiments will be modelled by various modelling teams from different Member States. 12 refs., 3 tabs

  10. Qualification testing facility for packages to be used for transport and storage of radioactive materials

    International Nuclear Information System (INIS)

    The radioactive materials (RAM) packaging have to comply to all modes and transport condition, routine or in accident conditions possibly to occur during transportation operations. It is well known that the safety in the transport of RAM is dependent on packaging appropriate for the contents being shipped rather than on operational and/or administrative actions required for the package. The quality of these packages - type A, B or C has to be proved by performing qualification tests in accordance with the ROMANIAN nuclear regulation conditions provided by CNCAN Order no. 357/22.12.2005- 'Norms for a Safe Transport of Radioactive Material', the IAEA Vienna Recommendation stipulated in the Safety standard TS-R-1- Regulation for the Safe Transport of Radioactive Material, 2005 Edition, and other applicable international recommendations. The paper will describe the components of the designed testing facilities, and the qualification testing to be performed for all type A, B and C packages subjected to the testing. In addition, a part of the qualification tests for a package (designed and manufactured in INR Pitesti) used for transport and storage of spent fuel LEU elements of a TRIGA nuclear reactor will be described and analyzed. Quality assurance and quality controls measures taken in order to meet technical specification provided by the design are also presented and commented. The paper concludes that the new Romanian Testing Facilities for RAM packages will comply with the national safe standards as well as with the IAEA applicable recommendation provided by the TS-R-1 safety standard. (author)

  11. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    International Nuclear Information System (INIS)

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year

  12. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    Energy Technology Data Exchange (ETDEWEB)

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

  13. Methane Emissions from Leak and Loss Audits of Natural Gas Compressor Stations and Storage Facilities.

    Science.gov (United States)

    Johnson, Derek R; Covington, April N; Clark, Nigel N

    2015-07-01

    As part of the Environmental Defense Fund's Barnett Coordinated Campaign, researchers completed leak and loss audits for methane emissions at three natural gas compressor stations and two natural gas storage facilities. Researchers employed microdilution high-volume sampling systems in conjunction with in situ methane analyzers, bag samples, and Fourier transform infrared analyzers for emissions rate quantification. All sites had a combined total methane emissions rate of 94.2 kg/h, yet only 12% of the emissions total resulted from leaks. Methane slip from exhausts represented 44% of the total emissions. Remaining methane emissions were attributed to losses from pneumatic actuators and controls, engine crankcases, compressor packing vents, wet seal vents, and slop tanks. Measured values were compared with those reported in literature. Exhaust methane emissions were lower than emissions factor estimates for engine exhausts, but when combined with crankcase emissions, measured values were 11.4% lower than predicted by AP-42 as applicable to emissions factors for four-stroke, lean-burn engines. Average measured wet seal emissions were 3.5 times higher than GRI values but 14 times lower than those reported by Allen et al. Reciprocating compressor packing vent emissions were 39 times higher than values reported by GRI, but about half of values reported by Allen et al. Though the data set was small, researchers have suggested a method to estimate site-wide emissions factors for those powered by four-stroke, lean-burn engines based on fuel consumption and site throughput. PMID:26148551

  14. ICPP calcined solids storage facility closure study. Volume III: Engineering design files

    International Nuclear Information System (INIS)

    The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project's scope of work. Should more accurate numbers be required, a new analysis would be necessary

  15. ICPP calcined solids storage facility closure study. Volume III: Engineering design files

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    The following information was calculated to support cost estimates and radiation exposure calculations for closure activities at the Calcined Solids Storage Facility (CSSF). Within the estimate, volumes were calculated to determine the required amount of grout to be used during closure activities. The remaining calcine on the bin walls, supports, piping, and floor was also calculated to approximate the remaining residual calcine volumes at different stages of the removal process. The estimates for remaining calcine and vault void volume are higher than what would actually be experienced in the field, but are necessary for bounding purposes. The residual calcine in the bins may be higher than was is experienced in the field as it was assumed that the entire bin volume is full of calcine before removal activities commence. The vault void volumes are higher as the vault roof beam volumes were neglected. The estimations that follow should be considered rough order of magnitude, due to the time constraints as dictated by the project`s scope of work. Should more accurate numbers be required, a new analysis would be necessary.

  16. CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.; Coleman, R.

    2011-03-31

    RadBall{trademark} is a novel technology that can locate and quantify unknown radioactive hazards within contaminated areas, hot cells, and gloveboxes. The device consists of a colander-like outer tungsten collimator that houses a radiation-sensitive polymer semi-sphere. The collimator has a number of small holes with tungsten inserts; as a result, specific areas of the polymer are exposed to radiation becoming increasingly more opaque in proportion to the absorbed dose. The polymer semi-sphere is imaged in an optical computed tomography scanner that produces a high resolution 3D map of optical attenuation coefficients. A subsequent analysis of the optical attenuation data using a reverse ray tracing or backprojection technique provides information on the spatial distribution of gamma-ray sources in a given area forming a 3D characterization of the area of interest. RadBall{trademark} was originally designed for dry deployments and several tests, completed at Savannah River National Laboratory and Oak Ridge National Laboratory, substantiate its modeled capabilities. This study involves the investigation of the RadBall{trademark} technology during four submerged deployments in two water filled cells at the DOE Hanford Site's Waste Encapsulation Storage Facility.

  17. Monitored Retrievable Storage (MRS) Facility and its impact on spent fuel transportation

    International Nuclear Information System (INIS)

    The Department of Energy has identified nine potential sites for a repository to permanently dispose of radioactive wastes. DOE has released several sets of maps and tables identifying expected transportation routes between nuclear reactors and repository sites. More recently, the DOE has announced three potential Monitored Retrievable Storage Facility (MRS) sites in the state of Tennessee. Obviously, if a large portion of the spent fuel is routed to Tennessee for consolidation and repackaging, there will be significant changes in the estimated routes. For typical scenarios, the number of shipments in the vicinity of the repository will be reduced. For example, with direct reactor to repository shipments, 995 highway and 262 rail shipments are expected to arrive at the repository annually. With a MRS these numbers are reduced to 201 and 30, respectively. The remaining consolidated fuel would be transported from the MRS in 22 dedicated trains (each train transporting five casks). Conversely, the MRS would result in an increase in the number of spent fuel shipments traveling through the eastern part of Tennessee. However, the operation of a MRS would significantly reduce the number of shipments through the central and western parts of the state

  18. Lining of the return water dam at the Onverwacht tailings storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Addis, Philip [Golder Associates Ltd (Canada)

    2011-07-01

    This paper deals with design and construction of a new tailings storage facility (TSF) at the Onverwacht site located on the south of the Nkomati mine in northeast South Africa. This TSF included a return water dam (RWD). The paper discusses the lining of the RWD at the Onverwacht TSF. The RWD was designed and constructed in agreement with the South African department of water affairs and forestry's dam safety office. A comprehensive leakage detection system was installed along with a 1.5mm HDPE geomembrane lining inside the dam. Constant monitoring of the flow rate in the leakage detection system was conducted during the construction and commissioning of the RWD. The multiple outlets for the leakage detection system revealed a leak in the dam's primary liner. The steps taken to repair the leak are mentioned. From the study, it can be concluded that full time site supervision is required even for a relatively simple single liner system.

  19. Current situation with the centralized storage facilities for non-power radioactive wastes in Latin American countries

    International Nuclear Information System (INIS)

    Full text: Several Latin American (LA) countries have been firmly committed to the peaceful applications of ionizing radiations in medicine, industry, agriculture and research in order to achieve socioeconomic development in diverse sectors. Consequently the use of radioactive materials and radiation sources as well as the production of radioisotopes and labeled compounds may always produce radioactive wastes which require adequate management and, in the end, disposal. However, there are countries in the Latin American region whose radioactive waste volumes do not easily justify a national repository. Moreover, such facilities are extremely expensive to develop. It is unlikely that such an option will become available in the foreseeable future for most of these countries, which do not have nuclear industries. Storage has long been incorporated as a step in the management of radioactive wastes. In the recent years, there have been developments that have led some countries to consider whether the roles of storage might be expanded to provide longer-term care of long-live radioactive wastes The aim of this paper is to discuss the current situation with the storage facilities/conditions for the radioactive wastes and disused sealed radioactive sources in Latin-American countries. In some cases a brief description of the existing facilities for certain countries are provided. In other cases, when no centralized facility exists, general information on the radioactive inventories and disused sealed sources is given. (author)

  20. Neutronic characterization and decay heat calculations in the in-vessel fuel storage facilities for MYRRHA/FASTEF

    International Nuclear Information System (INIS)

    Highlights: ► Monte Carlo design of reactor facilities. ► Neutron coupling assessment between critical core and fresh fuel in the storage vessels. ► Power contribution by induced fission from neutrons leaving the core, spontaneous fission and (α, n) sources. ► Power decay heat estimation for different reactor fuel cycles scenarios. ► Material damage assessment in the storage vessels. - Abstract: The main objective of the Central Design Team (CDT) project is to establish an engineering design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) that is the pilot plant of an experimental-scale of both an Accelerator Driven System (ADS) and a Lead Fast Reactor (LFR), based on the MYRRHA reactor concept, planned to be built during the next decade. The MYRRHA reactor concept is devoted to be a multi-purpose irradiation facility aimed at demonstrating the efficient transmutation of long-lived and high radiotoxicity minor actinides, fission products and the associated technology. An important issue regarding the reactor design of the MYRRHA/FASTEF experiment is the In-Vessel Fuel Storage Facilities (IVFSFs), both for fresh and spent fuel, as it might have an impact on the criticality of the overall system that must be quantified. In this work, the neutronic analysis of the in-vessel fuel storage facility and its coupling with the critical core was performed, using the state of the art Monte Carlo program MCNPX 2.6.0 and ORIGEN 2.2 computer code system for calculating the buildup and decay heat of spent fuel. Several parameters were analyzed, like the criticality behavior (namely the Keff), the neutron fluxes and their variations, the fission power production and the radiation damage (the displacements per atom). Finally, also the heat power generated by the fission products decay in the spent fuel was assessed.

  1. Aquifer storage and recovery (ASR): A strategic cost-effective facility to balance water production and demand for Sharjah

    OpenAIRE

    Almulla, Asam; Hamad, Ahmad; Gadalla, Mohamed

    2004-01-01

    Aquifer storage and recovery was evaluated as a strategic water storage facility and as a tool to reduce overallcost of water production. This work investigated the size, cost, and mode of operation required to run the proposed ASR. The best scenario was to build an ASR of 280 MIGs to balance the annual water demands and to cover up for a minimum of 25% of any major crisis that might occur. The ASR will have recharge from existing SEWA plant and an additional new seawater RO plant with a capa...

  2. Performance Evaluation of Lower-Energy Energy Storage Alternatives for Full-Hybrid Vehicles; NREL (National Renewable Energy Laboratory)

    Energy Technology Data Exchange (ETDEWEB)

    Gonder, J.; Cosgrove, J.; Pesaran, A.

    2014-02-11

    Automakers have been mass producing hybrid electric vehicles (HEVs) for well over a decade, and the technology has proven to be very effective at reducing per-vehicle fuel use. However, the incremental cost of HEVs such as the Toyota Prius or Ford Fusion Hybrid remains several thousand dollars higher than the cost of comparable conventional vehicles, which has limited HEV market penetration. The b b b b battery energy storage device is typically the component with the greatest contribution toward this cost increment, so significant cost reductions/performance improvements to the energy storage system (ESS) can correspondingly improve the vehicle-level cost/benefit relationship. Such an improvement would in turn lead to larger HEV market penetration and greater aggregate fuel savings. The United States Advanced Battery Consortium (USABC) and the U.S. Department of Energy (DOE) Energy Storage Program managers asked the National Renewable Energy Laboratory (NREL) to collaborate with a USABC Workgroup and analyze the trade-offs between vehicle fuel economy and reducing the decade-old minimum energy requirement for power-assist HEVs. NREL’s analysis showed that significant fuel savings could still be delivered from an ESS with much lower energy storage than the previous targets, which prompted USABC to issue a new set of lower-energy ESS (LEESS) targets that could be satisfied by a variety of technologies. With support from DOE, NREL has developed an HEV test platform for in-vehicle performance and fuel economy validation testing of the hybrid system using such LEESS devices. This presentation describes development of the vehicle test platform, and laboratory as well as in-vehicle evaluation results with alternate energy storage configurations as compared to the production battery system. The alternate energy storage technologies considered include lithium-ion capacitors -- i.e., asymmetric electrochemical energy storage devices possessing one electrode with battery

  3. Requalification of an existing underground liquid storage facility for the postulated site specific maximum potential earthquake event

    International Nuclear Information System (INIS)

    The seismic requalification of existing nuclear facilities basically aims at reviewing the adequacy of these facilities to withstand the seismic hazard with respect to current approach and methodology of a seismic design. The methodology of a seismic design of structures, systems and components (SSC) have been evolved over a number of years and several important safety-related facilities were designed and built according to the standards prevailing at the time of their construction. Therefore, it is desirable to reassess the capability of the SSC of older safety-related facilities and to ensure their integrity under seismic ground motion to meet the present statutory requirements. The present paper deals with the seismic response analysis and re-evaluation of design stresses for an existing underground liquid storage tank to assess the available safety margins for the postulated site specific maximum potential earthquake event i.e. safe shutdown earthquake (SSE)

  4. Pilot-benchmarking of the WENRA safety reference levels for the spent fuel intermediate storage facility Ahaus

    International Nuclear Information System (INIS)

    Full text: The Western European Nuclear Regulator's Association (WENRA) has 2007 issued the draft of the 'Waste and Spent Fuel Storage Safety Reference Levels'. The objective of WENRA is to strive for a harmonized safety level of nuclear facilities within the European Community and these Reference Levels are a benchmark method to demonstrate the achieved level for the regulatory system and the implementation as well. Safety Reference Levels exist at the moment for Reactor Safety, Waste Storage and Decommissioning in different stages of development. ENISS, the European Nuclear Installations Safety Standards Initiative, a FORATOM based special organisation of nuclear operators, has discussed these Safety Reference Levels very intensively with WENRA and the agreement was to make a implementation benchmark-exercise for the storage facilities before the authorities finally agree on the Reference Levels. This benchmark was scheduled for the year 2008. Because of the special situation in Germany where a large number of storage facilities is in operation the German authorities felt that it would be useful to initiate a Pilot-Benchmark to get first results on the feasibility of the Reference Levels and the burden imposed to authorities and operators by these benchmark-exercises. GNS, a subsidiary company of the utilities, agreed to step into this process on a voluntary basis with its storage facility for spent fuel in Ahaus. The exercise was done in a very efficient way and in good co-operation between the authorities, local and federal, and the operator. The results in terms of safety assessments have been very satisfactory showing the high degree of safety. Although the facility was for the first time licensed already in 1987 the compliance with nearly all Reference Levels from 2007 could be demonstrated. It became also clear that newer facilities would fulfil the desired safety standard too. Nevertheless, in spite of the good results the exercise revealed some weak

  5. An assessment of potential risk resulting from a maximum credible accident scenario at the proposed explosive waste storage facility (EWSF)

    International Nuclear Information System (INIS)

    Lawrence Livermore National Laboratory (LLNL) proposes to build, permit, and operate a storage facility for explosive wastes at LLNL's Explosive Test Site, Site 300. The facility would consist of four existing magazines, four new magazettes (small concrete vaults), and a new prefabricated metal building. Ash from on-site treatment of explosive waste would also be stored in the prefabricated metal building prior to sampling analysis, and shipment. The magazettes would be installed at each magazine-and would provide segregated storage for explosive waste types including detonators, actuators, and other initiating devices. The proposed facility would be used to store explosive wastes generated by the Hydrotest and Explosive Development Programs at LLNL prior to treatment on-site or shipment to permitted, commercial, off-site treatment facilities. Explosive wastes to be stored in the proposed facility represent a full spectrum of Department of Energy (DOE) and LLNL explosive wastes. This document identifies and evaluates the risk to human health and the environment associated with the operation of the proposed EWSF

  6. Assessment of the Proposed Design of a New Spent Sealed Radioactive Sources Storage Facility at Novi Han

    International Nuclear Information System (INIS)

    The NOVI HAN radioactive waste repository (NHRWR) in Bulgaria, built according to a Soviet design, was commissioned in 1964. The State Committee on the Use of Atomic Energy for Peaceful Purposes (CUAEPP) temporarily stopped operations at the repository from October 1994 until measures for improvement of the facility are undertaken. Since 1994, the Spent Sealed Radioactive Sources (SSRS) have been temporarily stored at the facilities at IRT-2000 research reactor of the Bulgarian Academy of Sciences (BAS) in Sofia. In view of the importance of the radiological risks associated with the present management of the SSRS in Bulgaria, the present study contract has been launched to critically review the proposal to provide a new interim storage facility for SSRS at NHRWR. A comprehensive critical review was performed of the feasibility study for the construction of a new SSRS facility at Novi Han, carried out by the local consultant engineering company (EQE), and detailed recommendations were made concerning the proposed new development at the site. The authors think that new concepts and procedures in the management of all categories of SSRS including smoke detectors have to be introduced, taking into account the regulatory framework and the inventories of existing and anticipated SSRS. This should be the basis for the technical specification of the new facilities for conditioning and storage of spent sealed radioactive sources (not only SHARS). (author)

  7. Final work plan : investigation of potential contamination at the former CCC/USDA grain storage facility in Hanover, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2008-11-19

    The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride (below the maximum contaminant level [MCL] of 5.0 {micro}g/L) were detected in two private wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In April 2007, the CCC/USDA collected near-surface soil samples at 1.8-2 ft BGL (below ground level) at 61 locations across the former CCC/USDA facility. All soil samples were analyzed by the rigorous gas chromatograph-mass spectrometer analytical method (purge-and-trap method). No contamination was found in soil samples above the reporting limit of 10 {micro}g/kg. In July 2007, the CCC/USDA sampled indoor air at nine residences on or adjacent to its former facility to address the residents concerns regarding vapor intrusion. Low levels of carbon tetrachloride were detected at four of the nine homes. Because carbon tetrachloride found in private wells and indoor air at the site might be linked to historical use of fumigants containing carbon tetrachloride at its former grain storage facility, the CCC/USDA is proposing to conduct an investigation to determine the source and extent of the carbon tetrachloride contamination associated with the former facility. This investigation will be conducted in accordance with the intergovernmental agreement between the KDHE and the Farm Service Agency (FSA) of the USDA. The investigation at Hanover will be performed, on behalf of the CCC/USDA, by the Environmental Science

  8. Economic and Environmental Evaluation of Flexible Integrated Gasification Polygeneration Facilities Equipped with Carbon Capture and Storage

    Science.gov (United States)

    Aitken, M.; Yelverton, W. H.; Dodder, R. S.; Loughlin, D. H.

    2014-12-01

    Among the diverse menu of technologies for reducing greenhouse gas (GHG) emissions, one option involves pairing carbon capture and storage (CCS) with the generation of synthetic fuels and electricity from co-processed coal and biomass. In this scheme, the feedstocks are first converted to syngas, from which a Fischer-Tropsch (FT) process reactor and combined cycle turbine produce liquid fuels and electricity, respectively. With low concentrations of sulfur and other contaminants, the synthetic fuels are expected to be cleaner than conventional crude oil products. And with CO2 as an inherent byproduct of the FT process, most of the GHG emissions can be eliminated by simply compressing the CO2 output stream for pipeline transport. In fact, the incorporation of CCS at such facilities can result in very low—or perhaps even negative—net GHG emissions, depending on the fraction of biomass as input and its CO2 signature. To examine the potential market penetration and environmental impact of coal and biomass to liquids and electricity (CBtLE), which encompasses various possible combinations of input and output parameters within the overall energy landscape, a system-wide analysis is performed using the MARKet ALlocation (MARKAL) model. With resource supplies, energy conversion technologies, end-use demands, costs, and pollutant emissions as user-defined inputs, MARKAL calculates—using linear programming techniques—the least-cost set of technologies that satisfy the specified demands subject to environmental and policy constraints. In this framework, the U.S. Environmental Protection Agency (EPA) has developed both national and regional databases to characterize assorted technologies in the industrial, commercial, residential, transportation, and generation sectors of the U.S. energy system. Here, the EPA MARKAL database is updated to include the costs and emission characteristics of CBtLE using figures from the literature. Nested sensitivity analysis is then

  9. Development of evaluation method for heat removal design of dry storage facilities. Pt. 3. Heat removal test on a cask storage system

    International Nuclear Information System (INIS)

    Based on a prospect of steady increase in the amount of spent fuel, it is expected to establish large capacity dry storage technologies for spent fuel. This report describes the result of heat removal test on a cask storage system using a 1/5 scale model. Cooling air induced by the natural convection strongly streamed along the floor from inlet to the center of the storage area, and the velocity gradually reduced as the stream reached to the center. On the other hand, upward flow induced by the buoyant force was observed in the boundary layer close to the surface of the cask models. On the feature of this flow pattern, heat transfer coefficient around cask models was expressed with a high degree of accuracy, in which the effect of horizontal stream was introduced in addition to that of the upward flow. Moreover, the effects of heat generation, geometrical arrangement of cask models, etc. on heat removal performance were made clear as the result of parametric tests. And in conclusion, velocity and temperature distributions in the assumed actual cask storage facility were evaluated in consideration of the similarity law applied to this test. (author)

  10. Effects of an alternative management of water storage on aridisol at the Bolivian Altiplane

    International Nuclear Information System (INIS)

    In the present study, we deal with a test as a base to recommend the preparation of soil for cultures different from the usual method. On a 5 year old fellow land, a parcel was ploughed before and another after the wet season. Differences on the water storage appear in both horizons of the studied aridisol, because of a structural improvement on the ploughed ground. During the five months of the rainy season, November through March, the values of water storage were between 5 and 12% higher in the ploughed soil

  11. Assessment of plutonium storage safety issues at Department of Energy facilities

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) mission for utilization and storage of nuclear materials has recently changed as a result of the end of the ''Cold War'' era. Past and current plutonium storage practices largely reflect a temporary, in-process, or in-use storage condition which must now be changed to accommodate longer-term storage. This report summarizes information concerning current plutonium metal and oxide storage practices which was presented at the Office of Defense programs (DP) workshop in Albuquerque, New Mexico on May 26-27, 1993 and contained in responses to questions by DP-62 from the field organizations

  12. Assessment of plutonium storage safety issues at Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    The Department of Energy (DOE) mission for utilization and storage of nuclear materials has recently changed as a result of the end of the ``Cold War`` era. Past and current plutonium storage practices largely reflect a temporary, in-process, or in-use storage condition which must now be changed to accommodate longer-term storage. This report summarizes information concerning current plutonium metal and oxide storage practices which was presented at the Office of Defense programs (DP) workshop in Albuquerque, New Mexico on May 26-27, 1993 and contained in responses to questions by DP-62 from the field organizations.

  13. Regulators Experiences in Licensing and Inspection of Dry Cask Storage Facilities

    International Nuclear Information System (INIS)

    The United States Nuclear Regulatory Commission (NRC), through the combination of a rigorous licensing and inspection program, ensures the safety and security of dry cask storage. NRC authorizes the storage of spent fuel at an independent spent fuel storage installation (ISFSI) under two licensing options: site-specific licensing and general licensing. In July 1986, the NRC issued the first site-specific license to the Surry Nuclear Power Plant in Virginia authorizing the interim storage of spent fuel in a dry storage cask configuration. Today, there are over 30 ISFSIs currently licensed by the NRC with over 700 loaded dry casks. Current projections identify over 50 ISFSIs by the year 2010. No releases of spent fuel dry storage cask contents or other significant safety problems from the storage systems in use today have been reported. This paper discusses the NRC licensing and inspection experiences. (authors)

  14. Regulatory body experiences in licensing and inspection of dry cask storage facilities

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission (NRC), through a rigorous licensing and inspection programme, ensures the safety and security of dry cask storage. The NRC authorizes the storage of spent fuel at an independent spent fuel storage installation (ISFSI) under two licensing options: site specific licensing and general licensing. In July 1986, the NRC issued the first site specific licence to the Surry Nuclear Power Plant in Virginia, authorizing the interim storage of spent fuel in a dry storage cask configuration. Presently, there are over 40 ISFSIs licensed by the NRC, with over 800 loaded dry casks. Current projections indicate that there will be over 50 ISFSIs by the year 2010. No releases of spent fuel dry storage cask contents or other significant safety problems from the storage systems in use today have been reported. The paper discusses the NRC's licensing and inspection experiences. (author)

  15. Regulators experiences in licensing and inspection of dry cask storage facilities

    International Nuclear Information System (INIS)

    The United States Nuclear Regulatory Commission (NRC), through the combination of a rigorous licensing and inspection program, ensures the safety and security of dry cask storage. NRC authorizes the storage of spent fuel at an independent spent fuel storage installation (ISFSI) under two licensing options: site-specific licensing and general licensing. In July 1986, the NRC issued the first site specific license to the Surry Nuclear Power Plant in Virginia authorizing the interim storage of spent fuel in a dry storage cask configuration. Today, there are over 30 ISFSIs currently licensed by the NRC with over 700 loaded dry casks. Current projections identify over 50 ISFSIs by the year 2010. No releases of spent fuel dry storage cask contents or other significant safety problems from the storage systems in use today have been reported. This paper discusses the NRC licensing and inspection experiences. (author)

  16. Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

  17. Coordination Between Wind Power, Hydro Storage Facility and Conventional Generating Units According to the Annual Growth Load

    Directory of Open Access Journals (Sweden)

    Shahrokh Shojaeean

    2013-04-01

    Full Text Available Considering the growing trend of the consumption of the electric power and the global tendency to substitute new renewable sources of energy, this paper proposes a Monte Carlo based method to determine an optimal level of this change. Considering the limitation of the wind farms in continuous supply of electric power, hydrostatic power storage facilities are used beside wind farms so that the electric power could be stored and fed in a continuous flow into power systems. Due to the gradual exclusion of conventional generators and 5 percent annual load increments, LOLE index was used in order to calculate the amount of the wind power and the capacity of the necessary power storage facility. To this end, LOLE index was calculated for the first year as the reference index for the estimation of the amount of wind power and the capacity of the storage facility in consequent years. For the upcoming years, calculations have been made to account for the gradual exclusion of conventional generators in proportion to load increments. The proposed method has been implemented and simulated on IEEE-RTS test system.

  18. Assessment of Energy Storage Alternatives in the Puget Sound Energy System

    Energy Technology Data Exchange (ETDEWEB)

    Balducci, Patrick J.; Jin, Chunlian; Wu, Di; Kintner-Meyer, Michael CW; Leslie, Patrick; Daitch, Charles

    2013-12-12

    As part of an ongoing study co-funded by the Bonneville Power Administration, under its Technology Innovation Grant Program, and the U.S. Department of Energy, the Pacific Northwest National Laboratory (PNNL) has developed an approach and modeling tool for assessing the net benefits of using energy storage located close to the customer in the distribution grid to manage demand. PNNL in collaboration with PSE and Primus Power has evaluated the net benefits of placing a zinc bromide battery system at two locations in the PSE system (Baker River / Rockport and Bainbridge Island). Energy storage can provide a number of benefits to the utility through the increased flexibility it provides to the grid system. Applications evaluated in the assessment include capacity value, balancing services, arbitrage, distribution deferral and outage mitigation. This report outlines the methodology developed for this study and Phase I results.

  19. The planning, construction, and operation of a radioactive waste storage facility for an Australian state radiation regulatory authority

    Energy Technology Data Exchange (ETDEWEB)

    Wallace, J.D.; Kleinschmidt, R.; Veevers, P. [Radiation Health, Queensland (Australia)

    1995-12-31

    Radiation regulatory authorities have a responsibility for the management of radioactive waste. This, more often than not, includes the collection and safe storage of radioactive sources in disused radiation devices and devices seized by the regulatory authority following an accident, abandonment or unauthorised use. The public aversion to all things radioactive, regardless of the safety controls, together with the Not In My Back Yard (NIMBY) syndrome combine to make the establishment of a radioactive materials store a near impossible task, despite the fact that such a facility is a fundamental tool for regulatory authorities to provide for the radiation safety of the public. In Queensland the successful completion and operational use of such a storage facility has taken a total of 8 years of concerted effort by the staff of the regulatory authority, the expenditure of over $2 million (AUS) not including regulatory staff costs and the cost of construction of an earlier separate facility. This paper is a summary of the major developments in the planning, construction and eventual operation of the facility including technical and administrative details, together with the lessons learned from the perspective of the overall project.

  20. Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)

    International Nuclear Information System (INIS)

    This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units, and the < 90 day accumulation areas

  1. Cleaning residual NaK in the fast flux test facility fuel storage cooling system

    International Nuclear Information System (INIS)

    The Fast Flux Test Facility (FFTF), located on the U.S. Department of Energy's Hanford Reservation, is a liquid metal-cooled test reactor. The FFTF was constructed to support the U.S. Liquid Metal Fast Breeder Reactor Program. The bulk of the alkali metal (sodium and NaK) has been drained and will be stored onsite prior to final disposition. Residual NaK needed to be removed from the pipes, pumps, heat exchangers, tanks, and vessels in the Fuel Storage Facility (FSF) cooling system. The cooling system was drained in 2004 leaving residual NaK in the pipes and equipment. The estimated residual NaK volume was 76 liters in the storage tank, 1.9 liters in the expansion tank, and 19-39 liters in the heat transfer loop. The residual NaK volume in the remainder of the system was expected to be very small, consisting of films, droplets, and very small pools. The NaK in the FSF Cooling System was not radiologically contaminated. The portions of the cooling system to be cleaned were divided into four groups: 1. The storage tank, filter, pump, and associated piping; 2. The heat exchanger, expansion tank, and associated piping; 3. Argon supply piping; 4. In-vessel heat transfer loop. The cleaning was contracted to Creative Engineers, Inc. (CEI) and they used their superheated steam process to clean the cooling system. It has been concluded that during the modification activities (prior to CEI coming onsite) to prepare the NaK Cooling System for cleaning, tank T-914 was pressurized relative to the In-Vessel NaK Cooler and NaK was pushed from the tank back into the Cooler and that on November 6, 2005, when the gas purge through the In-Vessel NaK Cooler was increased from 141.6 slm to 283.2 slm, NaK was forced from the In-Vessel NaK Cooler and it contacted water in the vent line and/or scrubber. The gases from the reaction then traveled back through the vent line coating the internal surface of the vent line with NaK and NaK reaction products. The hot gases also exited the

  2. License procedure for spent fuel storage facilities in the Czech Republic from the competent authority point of view

    International Nuclear Information System (INIS)

    Full text: The Policy, approved by the Czech Government on 15 May 2002 (Government Resolution No. 487/2002), is the fundamental document defining a strategy of the State and its agencies in spent fuel and radioactive waste management through 2025. The main principles of the Policy for the spent fuel management are: - Spent fuel management is provided by nuclear power plants (NPPs) authorized for operation in the Czech Republic. Spent fuel shall be stored in dry storage facilities at the NPPs, in storage only casks or in transport and storage casks. -Possibilities for spent fuel reprocessing are monitored and assessed, as well as the use of new technologies leading to the reduction of spent fuel volume and toxicity. A deep repository shall be put into operation in 2065. -The costs of activities associated with disposal of spent fuel are paid from the nuclear account, a financial source created by generators of spent fuel in agreement with the Atomic Act and established government Order. The Ministry of Finance manages the nuclear account, as a part of the state financial assets and liabilities. This assures that the costs of disposition for wastes generated now will not be transferred to future generations. - The general public is kept informed about the Policy and about its fulfillment. The license procedure for spent fuel storage facilities is governed by three acts: - Act No. 100/2001 Coll., on assessment of impacts on the environment, - Construction Act (No. 50/1976 Coll.), and - Act No. 18/1997 Coll. (Atomic Act) The procedure consists in practice of four stages: - Assessment of impacts of the planned construction on the Environmental Impact Assessment (EIA) process, - Siting decision, - Construction permit, and - Operations permit. Interim spent fuel storage facility at Dukovany (ISFSF). The first preparatory works started in May 1991. In October 1992, a public hearing took place to discuss the environmental impact of the ISFSF based on an EIA study. In

  3. Neutron Absorbing Ability Variation in Neutron Absorbing Material Caused by the Neutron Irradiation in Spent Fuel Storage Facility

    International Nuclear Information System (INIS)

    In spent fuel storage facility like high density spent fuel storage racks and dry storage casks, spent fuels are stored with neutron absorbing materials installed as a part of those facilities, and they are used for absorbing neutrons emitted from spent fuels. Usually structural material with neutron absorbing material of racks and casks are located around spent fuels, so it is irradiated by neutrons for long time. Neutron absorbing ability could be changed by the variation of nuclide composition in neutron absorbing material caused by the irradiation of neutrons. So, neutron absorbing materials are continuously faced with spent fuels with boric acid solution or inert gas environment. Major nuclides in neutron absorbing material are Al27, C12, B11, B10 and they are changed to numerous other ones as radioactive decay or neutron absorption reaction. The B10 content in neutron absorbing material dominates the neutron absorbing ability, so, the variation of nuclide composition including the decrease of B10 content is the critical factor on neutron absorbing ability. In this study, neutron flux in spent fuel, the activation of neutron absorbing material and the variation of nuclide composition are calculated. And, the minimum neutron flux causing the decrease of B10 content is calculated in spent fuel storage facility. Finally, the variation of neutron multiplication factor is identified according to the one of B10 content in neutron absorbing material. The minimum neutron flux to impact the neutron absorbing ability is 1010 order, however, usual neutron flux from spent fuel is 108 order. Therefore, even though neutron absorbing material is irradiated for over 40 years, B10 content is little decreased, so, initial neutron absorbing ability could be kept continuously

  4. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    International Nuclear Information System (INIS)

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis

  5. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-06-02

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  6. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-04-09

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  7. Hazardous Material Storage Facilities and Sites, Shane Root- Root Spraying Service, Published in 2008, 1:2400 (1in=200ft) scale, Lane County.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Hazardous Material Storage Facilities and Sites dataset, published at 1:2400 (1in=200ft) scale, was produced all or in part from Not Provided information as of...

  8. Gas Storage Facilities, LP and LNG, tank farm; sparks, Published in 2006, 1:1200 (1in=100ft) scale, Washoe County.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Gas Storage Facilities, LP and LNG dataset, published at 1:1200 (1in=100ft) scale, was produced all or in part from Published Reports/Deeds information as of...

  9. Characterization of spent fuel assemblies for storage facilities using non destructive assay

    International Nuclear Information System (INIS)

    Many non destructive assay (NDA) techniques have been developed by the French Atomic Energy Commission (CEA) for spent fuel characterization and management. Passive and active neutron methods as well as gamma spectrometric methods have been carried out and applied to industrial devices like PYTHONTM and NAJA. Many existing NDA methods can be successfully applied to storage, but the most promising are the neutron methods combined with on line evolution codes. For dry storage applications, active neutron measurements require further R and D to achieve accurate results. Characterization data given by NDA instruments can now be linked to automatic fuel recognition. Both information can feed the storage management software in order to meet the storage operation requirements like: fissile mass inventory, operators declaration consistency or automatic selection of proper storage conditions. (author)

  10. Hazardous waste storage facility accident scenarios for the U.S. Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement

    Energy Technology Data Exchange (ETDEWEB)

    Policastro, A.; Roglans-Ribas, J.; Marmer, D.; Lazaro, M.; Mueller, C. [Argonne National Lab., IL (United States); Freeman, W. [Univ. of Illinois, Chicago, IL (United States). Dept. of Chemistry

    1994-03-01

    This paper presents the methods for developing accident categories and accident frequencies for internally initiated accidents at hazardous waste storage facilities (HWSFs) at US Department of Energy (DOE) sites. This categorization is a necessary first step in evaluating the risk of accidents to workers and the general population at each of the sites. This risk evaluation is part of the process of comparing alternative management strategies in DOE`s Environmental Restoration and Waste Management (EM) Programmatic Environmental Impact Statement (PEIS). Such strategies involve regionalization, decentralization, and centralization of waste treatment, storage, and disposal activities. Potential accidents at the HWSFs at the DOE sites are divided into categories of spill alone, spill plus fire, and other event combinations including spill plus fire plus explosion, fire only, spill and explosion, and fire and explosion. One or more accidents are chosen to represent the types of accidents for FY 1992 for 12 DOE sites were studied to determine the most representative set of possible accidents at all DOE sites. Each accident scenario is given a probability of occurrence that is adjusted, depending on the throughput and waste composition that passes through the HWSF at the particular site. The justification for the probabilities chosen is presented.

  11. Hazardous waste storage facility accident scenarios for the U.S. Department of Energy Environmental Restoration and Waste Management Programmatic Environmental Impact Statement

    International Nuclear Information System (INIS)

    This paper presents the methods for developing accident categories and accident frequencies for internally initiated accidents at hazardous waste storage facilities (HWSFs) at US Department of Energy (DOE) sites. This categorization is a necessary first step in evaluating the risk of accidents to workers and the general population at each of the sites. This risk evaluation is part of the process of comparing alternative management strategies in DOE's Environmental Restoration and Waste Management (EM) Programmatic Environmental Impact Statement (PEIS). Such strategies involve regionalization, decentralization, and centralization of waste treatment, storage, and disposal activities. Potential accidents at the HWSFs at the DOE sites are divided into categories of spill alone, spill plus fire, and other event combinations including spill plus fire plus explosion, fire only, spill and explosion, and fire and explosion. One or more accidents are chosen to represent the types of accidents for FY 1992 for 12 DOE sites were studied to determine the most representative set of possible accidents at all DOE sites. Each accident scenario is given a probability of occurrence that is adjusted, depending on the throughput and waste composition that passes through the HWSF at the particular site. The justification for the probabilities chosen is presented

  12. MK-III heat transport system modification work in JOYO. Installation of radioactive waste material storage facility for old IHXs

    International Nuclear Information System (INIS)

    The MK-III project has been proceeding to improve the irradiation capability of the experimental fast reactor JOYO since 1987. The MK-III project has three major purposes such as increasing high neutron flux, improvement of plant availability factor and upgrading in irradiation techniques. The increase of high neutron flux increased thermal output of core from 100 MW to 140 MW. The main components in the cooling system such as IHXs (Intermediate Heat Exchanger) and DHXs(Dump Heat Exchanger) were replaced in MK-III modification in order to increase heat removal capability. These components replacement has been safely carried out from October 30, 2000 to September 21, 2001. The radioactive corrosion products such as 60Co and 54Mn, and radioactive sodium were resided on the inner surface of old IHX which had been already removed from the system in the MK-III modification work. We may dismantle old IHX and remove the residual sodium only after enough decrease of their radioactivity. We have to store it safely over a fairly long period. Therefore, we examined the safety storage way of old IHX. Based on the examination, we selected the free space inside the pump cleaning pit in the maintenance building as a radioactive waste storage facility. Before the modification work of pump cleaning pit, we needed the permission of design and the construction as well as the change of establishment for installation of radioactive waste storage facility. Modification work of the pump cleaning pit including removal of the interfering pipes were done for two months from April to May, 2000. Enlargement work of opening in pump cleaning pit and coating work of the wall surface were done from August, 2000 to January, 2001. Installation work of the metallic plate for shielding was done for two months from April to May of 2001 after installation of old IHXs in the pump cleaning pit. This report shows the records of installation of radioactive waste storage facility for IHXs from the planning

  13. Intended long term performances of cementitious engineered barriers for future storage and disposal facilities for radioactive wastes in Romania

    Directory of Open Access Journals (Sweden)

    Sociu F.

    2013-07-01

    Full Text Available Considering the EU statements, Romania is engaged to endorse in the near future the IAEA relevant publications on geological repository (CNCANa, to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Currently, for example, spent fuel is wet stored for 6 years and after this period it is transported to dry storage in MACSTOR-200 (a concrete monolithic module where it is intended to remain at least 50 years. The present situation for radioactive waste management in Romania is reviewed in the present paper. Focus will be done on existent disposal facilities but, also, on future facilities planned for storage / disposal of radioactive wastes. Considering specific data for Romanian radioactive waste inventory, authors are reviewing the advance in the radioactive waste management in Romania considering its particularities. The team tries to highlight the expected limitations and unknown data related with cementitious engineered barriers that has to be faced in the near future incase of interim storage or for the upcoming long periods of disposal.

  14. Transport of a solute pulse through the bentonite barrier of deep geological high-level waste storage facilities in granite

    International Nuclear Information System (INIS)

    Spain like Sweden, Finland, Canada and other countries has opted for an open nuclear fuel cycle, and to store the unreprocessed spent fuel in a stable geological formation. Sweden, Finland and Canada have chosen granite rock for their high-level waste storage facilities. Their Performance Assessment of disposal systems have all obtained to the same result. The greatest annual doses are caused by I 129 in the gap between the fuel rods and the cladding. The reference concept for the Spanish high-level waste storage facility in granite provides for final storage in a granite mass at a depth of 500 m in carbon steel capsules in horizontal tunnels surrounded by a bentonite buffer. It the capsule fails due to generalised corrosion, an not giving credit for the cladding, the I 129 and other radionuclides in the gap would pass immediately into the surrounding water. This paper describes the modelling of the transport of the solute through the bentonite around the capsule to determine the fraction that crosses the bentonite each year. It also analyses the sensitivity of the results to the boundary condition adopted and changes in the values of the relevant parameters. (Author)

  15. An assessment of alternatives and technologies for replacing ozone- depleting substances at DOE facilities

    Energy Technology Data Exchange (ETDEWEB)

    Purcell, C.W.; Miller, K.B.; Friedman, J.R.; Rapoport, R.D.; Conover, D.R.; Hendrickson, P.L. (Pacific Northwest Lab., Richland, WA (United States)); Koss, T.C. (USDOE Assistant Secretary for Environment, Safety, and Health, Washington, DC (United States). Office of Environmental Guidance)

    1992-10-01

    Title VI of the Clean Air Act, as amended, mandates a production phase-out for ozone-depleting substances (ODSs). These requirements will have a significant impact on US Department of Energy (DOE) facilities. Currently, DOE uses ODSs in three major activities: fire suppression (halon), refrigeration and cooling (chlorofluorocarbons [CFCs]), and cleaning that requires solvents (CFCs, methyl chloroform, and carbon tetrachloride). This report provides basic information on methods and strategies to phase out use of ODSs at DOE facilities.

  16. 40 CFR 63.11087 - What requirements must I meet for gasoline storage tanks if my facility is a bulk gasoline...

    Science.gov (United States)

    2010-07-01

    ...) If your gasoline storage tank is subject to, and complies with, the control requirements of 40 CFR... gasoline storage tanks if my facility is a bulk gasoline terminal, pipeline breakout station, or pipeline... CATEGORIES (CONTINUED) National Emission Standards for Hazardous Air Pollutants for Source Category:...

  17. Box Energy: rental of energy-storage systems and alternative fuel technologies for vehicles; Box-energy. Rental of energy. Storage systems and alternative-fuel. Technologies for vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Bautz, R.

    2004-07-01

    This report for the Swiss Federal Office of Energy (SFOE) presents the results of study on the rental of energy-storage systems and alternative fuel technologies for vehicles. Experience gained in the area of battery-rental is discussed. The aims of the 'Box Energy' project are described, as is its market environment. The 'Box Energy' concept is described and possible customers and partners listed. Logistics aspects are discussed. The organisation of 'Box Energy' is described and the concept's chances and weaknesses are discussed. The launching of a pilot project in Switzerland is discussed. Recommendations on further work to be done are made.

  18. Monitored retrievable storage (MRS) facility and salt repository integration: Engineering study report

    International Nuclear Information System (INIS)

    This MRS Facility and Salt Repository Integration Study evaluates the impacts of an integrated MRS/Salt Repository Waste Management System on the Salt Repository Surface facilities' design, operations, cost, and schedule. Eight separate cases were studied ranging from a two phase repository design with no MRS facility to a design in which the repository only received package waste from the MRS facility for emplacement. The addition of the MRS facility to the Waste Management System significantly reduced the capital cost of the salt repository. All but one of the cases studied were capable of meeting the waste acceptance data. The reduction in the size and complexity of the Salt Repository waste handling building with the integration of the MRS facility reduces the design and operating staff requirements. 7 refs., 35 figs., 43 tabs

  19. Final environmental impact statement. Proton--Proton Storage Accelerator Facility (ISABELLE), Brookhaven National Laboratory, Upton, New York

    Energy Technology Data Exchange (ETDEWEB)

    Liverman, James L.

    1978-08-01

    An Environmental Impact Statement for a proposed research facility (ISABELLE) to be built at Brookhaven National Laboratory (BNL) is presented. It was prepared by the Department of Energy (DOE) following guidelines issued for such analyses. In keeping with DOE policy, this statement presents a concise and issues-oriented analysis of the significant environmental effects associated with the proposed action. ISABELLE is a proposed physics research facility where beams of protons collide providing opportunities to study high energy interactions. The facility would provide two interlaced storage ring proton accelerators, each with an energy up to 400 GeV intersecting in six experimental areas. The rings are contained in a tunnel with a circumference of 3.8 km (2.3 mi). The facility will occupy 250 ha (625 acres) in the NW corner of the existing BNL site. A draft Environmental Impact Statement for this proposed facility was issued for public review and comment by DOE on February 21, 1978. The principal areas of concern expressed were in the areas of radiological impacts and preservation of cultural values. After consideration of these comments, appropriate actions were taken and the text of the statement has been amended to reflect the comments. The text was annotated to indicate the origin of the comment. The Appendices contain a glossary of terms and listings of metric prefixes and conversions and symbols and abbreviations.

  20. Final environmental impact statement. Proton--Proton Storage Accelerator Facility (ISABELLE), Brookhaven National Laboratory, Upton, New York

    International Nuclear Information System (INIS)

    An Environmental Impact Statement for a proposed research facility (ISABELLE) to be built at Brookhaven National Laboratory (BNL) is presented. It was prepared by the Department of Energy (DOE) following guidelines issued for such analyses. In keeping with DOE policy, this statement presents a concise and issues-oriented analysis of the significant environmental effects associated with the proposed action. ISABELLE is a proposed physics research facility where beams of protons collide providing opportunities to study high energy interactions. The facility would provide two interlaced storage ring proton accelerators, each with an energy up to 400 GeV intersecting in six experimental areas. The rings are contained in a tunnel with a circumference of 3.8 km (2.3 mi). The facility will occupy 250 ha (625 acres) in the NW corner of the existing BNL site. A draft Environmental Impact Statement for this proposed facility was issued for public review and comment by DOE on February 21, 1978. The principal areas of concern expressed were in the areas of radiological impacts and preservation of cultural values. After consideration of these comments, appropriate actions were taken and the text of the statement has been amended to reflect the comments. The text was annotated to indicate the origin of the comment. The Appendices contain a glossary of terms and listings of metric prefixes and conversions and symbols and abbreviations