WorldWideScience

Sample records for underground dry storage

  1. Inherent security benefits of underground dry storage of nuclear materials

    International Nuclear Information System (INIS)

    Moore, R.D.; Zahn, T.

    1997-07-01

    This paper, augmented by color slides and handouts, will examine the inherent security benefits of underground dry storage of nuclear materials. Specific items to be presented include: the successful implementation of this type of storage configuration at Argonne National Laboratory - West; facility design concepts with security as a primary consideration; physical barriers achieved by container design; detection, assessment, and monitoring capabilities; and open-quotes self protectionclose quotes strategies. This is a report on the security features of such a facility. The technical operational aspects of the facility are beyond the scope of this paper

  2. Underground storage

    Energy Technology Data Exchange (ETDEWEB)

    1965-06-10

    A procedure is described for making an underground storage cavity in a soluble formation. Two holes are drilled, and fluid is pumped into the first hole. This fluid is a non-solute for the formation material. Then pressure is applied to the fluid until the formation is fractured in the direction of the second hole. More non-solute fluid is injected to complete the fracture between the 2 holes. A solute fluid is then circulated between the 2 holes, which results in removal of that part of the formation next to the fracture and the forming of a chamber.

  3. Underground storage tanks

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Environmental contamination from leaking underground storage tanks poses a significant threat to human health and the environment. An estimated five to six million underground storage tanks containing hazardous substances or petroleum products are in use in the US. Originally placed underground as a fire prevention measure, these tanks have substantially reduced the damages from stored flammable liquids. However, an estimated 400,000 underground tanks are thought to be leaking now, and many more will begin to leak in the near future. Products released from these leaking tanks can threaten groundwater supplies, damage sewer lines and buried cables, poison crops, and lead to fires and explosions. As required by the Hazardous and Solid Waste Amendments (HSWA), the EPA has been developing a comprehensive regulatory program for underground storage tanks. The EPA proposed three sets of regulations pertaining to underground tanks. The first addressed technical requirements for petroleum and hazardous substance tanks, including new tank performance standards, release detection, release reporting and investigation, corrective action, and tank closure. The second proposed regulation addresses financial responsibility requirements for underground petroleum tanks. The third addressed standards for approval of state tank programs

  4. Underground Storage Tanks in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Underground storage tank (UST) sites which store petroleum in Iowa. Includes sites which have been reported to DNR, and have active or removed underground storage...

  5. Dry storage

    International Nuclear Information System (INIS)

    Arnott, Don.

    1985-01-01

    The environmental movement has consistently argued against disposal of nuclear waste. Reasons include its irretrievability in the event of leakage, the implication that reprocessing will continue and the legitimacy attached to an expanding nuclear programme. But there is an alternative. The author here sets out the background and a possible future direction of a campaign based on a call for dry storage. (author)

  6. Regulated underground storage tanks

    International Nuclear Information System (INIS)

    1992-06-01

    This guidance package is designed to assist DOE Field operations by providing thorough guidance on the underground storage tank (UST) regulations. [40 CFR 280]. The guidance uses tables, flowcharts, and checklists to provide a ''roadmap'' for DOE staff who are responsible for supervising UST operations. This package is tailored to address the issues facing DOE facilities. DOE staff should use this guidance as: An overview of the regulations for UST installation and operation; a comprehensive step-by-step guidance for the process of owning and operating an UST, from installation to closure; and a quick, ready-reference guide for any specific topic concerning UST ownership or operation

  7. Underground Storage Tanks - Storage Tank Locations

    Data.gov (United States)

    NSGIC Education | GIS Inventory — 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...

  8. Underground storage tank program

    International Nuclear Information System (INIS)

    Lewis, M.W.

    1994-01-01

    Underground storage tanks, UST'S, have become a major component of the Louisville District's Environmental Support Program. The District's Geotechnical and Environmental Engineering Branch has spear-headed an innovative effort to streamline the time, effort and expense for removal, replacement, upgrade and associated cleanup of USTs at military and civil work installations. This program, called Yank-A-Tank, creates generic state-wide contracts for removal, remediation, installation and upgrade of storage tanks for which individual delivery orders are written under the basic contract. The idea is to create a ''JOC type'' contract containing all the components of work necessary to remove, reinstall or upgrade an underground or above ground tank. The contract documents contain a set of generic specifications and unit price books in addition to the standard ''boiler plate'' information. Each contract requires conformance to the specific regulations for the state in which it is issued. The contractor's bid consists of a bid factor which in the multiplier used with the prices in the unit price book. The solicitation is issued as a Request for Proposal (RPP) which allows the government to select a contractor based on technical qualification an well as bid factor. Once the basic contract is awarded individual delivery orders addressing specific areas of work are scoped, negotiated and awarded an modifications to the original contract. The delivery orders utilize the prepriced components and the contractor's factor to determine the value of the work

  9. Cursory search for carbonates suitable for developing dry underground storage space in the midcontinent, U.S.A

    International Nuclear Information System (INIS)

    Byerly, D.W.

    1975-01-01

    This search for carbonate strata for possible use as nuclear waste repository was prompted by studies of two sites: a deep limestone mine near Barberton, Ohio, and near-surface drift limestone mines near Kansas City, Missouri. Geomorphology, bedrock geology, tectonics and seismicity, and hydrology of the two sites are discussed. It is concluded that the geology of the Barberton site probably offers the greater potential for dry storage over a longer duration of time. Carbonate rocks in North America are evaluated briefly using the criteria just developed, and areas in the midcontinent warranting further study are identified. 26 figures

  10. Underground storage of heat

    International Nuclear Information System (INIS)

    Despois, J.; Nougarede, F.

    1976-01-01

    The interest laying in heat storage is envisaged taking account of the new energy context, with a view to optimizing the use of production means of heat sources hardly modulated according to the demand. In such a way, a natural medium, without any constructions cost but only an access cost is to be used. So, porous and permeable rocky strata allowing the use of a pressurized water flow as a transfer fluid are well convenient. With such a choice high temperatures (200 deg C) may be obtained, that are suitable for long transmissions. A mathematical model intended for solving the conservation equations in the case of heat storage inside a confined water layer is discussed. An approach of the operating conditions of storage may involve either a line-up arrangement (with the hot drilling at the center, the cold drillings being aligned on both sides) or a radial arrangement (with cold drillings at the peripheral edge encircling the hot drilling at the center of the layer). The three principal problems encountered are: starting drilling, and the circuit insulation and control [fr

  11. Underground storage of carbon dioxide

    Energy Technology Data Exchange (ETDEWEB)

    Tanaka, Shoichi [Univ. of Tokyo, Hongo, Bunkyo-ku (Japan)

    1993-12-31

    Desk studies on underground storage of CO{sub 2} were carried out from 1990 to 1991 fiscal years by two organizations under contract with New Energy and Indestrial Technology Development Organization (NEDO). One group put emphasis on application of CO{sub 2} EOR (enhanced oil recovery), and the other covered various aspects of underground storage system. CO{sub 2} EOR is a popular EOR method in U.S. and some oil countries. At present, CO{sub 2} is supplied from natural CO{sub 2} reservoirs. Possible use of CO{sub 2} derived from fixed sources of industries is a main target of the study in order to increase oil recovery and storage CO{sub 2} under ground. The feasibility study of the total system estimates capacity of storage of CO{sub 2} as around 60 Gton CO{sub 2}, if worldwide application are realized. There exist huge volumes of underground aquifers which are not utilized usually because of high salinity. The deep aquifers can contain large amount of CO{sub 2} in form of compressed state, liquefied state or solution to aquifer. A preliminary technical and economical survey on the system suggests favorable results of 320 Gton CO{sub 2} potential. Technical problems are discussed through these studies, and economical aspects are also evaluated.

  12. 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

    ... 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 ENVIRONMENTAL... underground storage tank or underground storage tank system or facility or property on which an underground...

  13. Underground storage of nuclear waste

    International Nuclear Information System (INIS)

    Russell, J.E.

    1977-06-01

    The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commerical radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects. 7 refs., 5 figs

  14. Underground storage of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Russell, J E

    1977-12-01

    The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commercial radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects.

  15. Underground storage tank management plan

    International Nuclear Information System (INIS)

    1994-09-01

    The Underground Storage Tank (UST) Management Program at the Oak Ridge Y-12 Plant was established to locate UST systems in operation at the facility, to ensure that all operating UST systems are free of leaks, and to establish a program for the removal of unnecessary UST systems and upgrade of UST systems that continue to be needed. The program implements an integrated approach to the management of UST systems, with each system evaluated against the same requirements and regulations. A common approach is employed, in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance, when corrective action is mandated. This Management Plan outlines the compliance issues that must be addressed by the UST Management Program, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Management Plan provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. (There are no underground radioactive waste UST systems located at Y-12.) The plan is divided into four major sections: (1) regulatory requirements, (2) implementation requirements, (3) Y-12 Plant UST Program inventory sites, and (4) UST waste management practices. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Management Program, and the procedures and guidance used for compliance with applicable regulations

  16. Underground storage tank management plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    The Underground Storage Tank (UST) Management Program at the Oak Ridge Y-12 Plant was established to locate UST systems in operation at the facility, to ensure that all operating UST systems are free of leaks, and to establish a program for the removal of unnecessary UST systems and upgrade of UST systems that continue to be needed. The program implements an integrated approach to the management of UST systems, with each system evaluated against the same requirements and regulations. A common approach is employed, in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance, when corrective action is mandated. This Management Plan outlines the compliance issues that must be addressed by the UST Management Program, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Management Plan provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. (There are no underground radioactive waste UST systems located at Y-12.) The plan is divided into four major sections: (1) regulatory requirements, (2) implementation requirements, (3) Y-12 Plant UST Program inventory sites, and (4) UST waste management practices. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Management Program, and the procedures and guidance used for compliance with applicable regulations.

  17. State Certification of Underground Storage Tanks

    National Research Council Canada - National Science Library

    Granetto, Paul

    1998-01-01

    .... The audit was performed in response to a Senate Armed Services Committee inquiry about whether state environmental regulatory agencies would be able to certify that DoD underground storage tanks...

  18. Leaking Underground Storage Tank Sites in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Leaking Underground Storage Tank (LUST) sites where petroleum contamination has been found. There may be more than one LUST site per UST site.

  19. Underground storage of radioactive wastes

    International Nuclear Information System (INIS)

    Dietz, D.N.

    1977-01-01

    An introductory survey of the underground disposal of radioactive wastes is given. Attention is paid to various types of radioactive wastes varying from low to highly active materials, as well as mining techniques and salt deposits

  20. 40 CFR 280.230 - Operating an underground storage tank or underground storage tank system.

    Science.gov (United States)

    2010-07-01

    ... underground storage tank or underground storage tank system. (a) Operating an UST or UST system prior to...) Operating an UST or UST system after foreclosure. The following provisions apply to a holder who, through..., the purchaser must decide whether to operate or close the UST or UST system in accordance with...

  1. Energy Policy Act of 2005 and Underground Storage Tanks (USTs)

    Science.gov (United States)

    The Energy Policy Act of 2005 significantly affected federal and state underground storage tank programs, required major changes to the programs, and is aimed at reducing underground storage tank releases to our environment.

  2. Reflection Phenomena in Underground Pumped Storage Reservoirs

    Directory of Open Access Journals (Sweden)

    Elena Pummer

    2018-04-01

    Full Text Available Energy storage through hydropower leads to free surface water waves in the connected reservoirs. The reason for this is the movement of water between reservoirs at different elevations, which is necessary for electrical energy storage. Currently, the expansion of renewable energies requires the development of fast and flexible energy storage systems, of which classical pumped storage plants are the only technically proven and cost-effective technology and are the most used. Instead of classical pumped storage plants, where reservoirs are located on the surface, underground pumped storage plants with subsurface reservoirs could be an alternative. They are independent of topography and have a low surface area requirement. This can be a great advantage for energy storage expansion in case of environmental issues, residents’ concerns and an unusable terrain surface. However, the reservoirs of underground pumped storage plants differ in design from classical ones for stability and space reasons. The hydraulic design is essential to ensure their satisfactory hydraulic performance. The paper presents a hybrid model study, which is defined here as a combination of physical and numerical modelling to use the advantages and to compensate for the disadvantages of the respective methods. It shows the analysis of waves in ventilated underground reservoir systems with a great length to height ratio, considering new operational aspects from energy supply systems with a great percentage of renewable energies. The multifaceted and narrow design of the reservoirs leads to complex free surface flows; for example, undular and breaking bores arise. The results show excessive wave heights through wave reflections, caused by the impermeable reservoir boundaries. Hence, their knowledge is essential for a successful operational and constructive design of the reservoirs.

  3. Leak detection for underground storage tanks

    International Nuclear Information System (INIS)

    Durgin, P.B.; Young, T.M.

    1993-01-01

    This symposium was held in New Orleans, Louisiana on January 29, 1992. The purpose of this conference was to provide a forum for exchange of state-of-the-art information on leak detection for underground storage tanks that leaked fuel. A widespread concern was protection of groundwater supplies from these leaking tanks. In some cases, the papers report on research that was conducted two or three years ago but has never been adequately directed to the underground storage tank leak-detection audience. In other cases, the papers report on the latest leak-detection research. The symposium was divided into four sessions that were entitled: Internal Monitoring; External Monitoring; Regulations and Standards; and Site and Risk Evaluation. Individual papers have been cataloged separately for inclusion in the appropriate data bases

  4. Underground storage of natural gas and LPG

    International Nuclear Information System (INIS)

    1990-01-01

    The Symposium attended by over 200 participants from 23 member countries of the Economic Commission for Europe (ECE), representatives from Australia, Iraq, Israel, Kuwait as well as from 5 international organizations, provided an opportunity for existing and prospective gas markets in the ECE region to exchange experience and information on current trends and developments in natural gas and liquefied petroleum gas underground storage, especially in technical and regulatory matters, including economic, market and social considerations, that influence the planning, development and operations of gas storage facilities. Environmental and safety factors associated with such operations were also examined. A separate abstract was prepared for each of the presented papers. Refs, figs and tabs

  5. Economics of dry storage systems

    International Nuclear Information System (INIS)

    Moore, G.R.; Winders, R.C.

    1980-01-01

    This paper postulates a dry storage application suitable as a regional away-from-reactor storage (AFR), develops an economical system design concept and estimates system costs. The system discussed uses the experience gained in the dry storage research activities and attempts to present a best foot forward system concept. The major element of the system is the Receiving and Packaging Building. In this building fuel assemblies are removed from transportation casks and encapsulated for storage. This facility could be equally applicable to silo, vault, or caisson storage. However the caisson storage concept has been chosen for discussion purposes

  6. Underground storage of natural gas in Italy

    International Nuclear Information System (INIS)

    Henking, E.

    1992-01-01

    After first relating the importance of natural gas storage to the viability of Italian industrial activities, this paper discusses the geo-physical nature of different types of underground cavities which can be used for natural gas storage. These include depleted petroleum and natural gas reservoirs, aquifers and abandoned mines. Attention is given to the geologic characteristics and physical characteristics such as porosity, permeability and pressure that determine the suitability of any given storage area, and to the techniques used to resolve problems relative to partially depleted reservoirs, e.g., the presence of oil, water and salt. A review is made of Italy's main storage facilities. This review identifies the various types of storage techniques, major equipment, operating and maintenance practices. A look is then given at Italy's plans for the development of new facilities to meet rising demand expected to reach 80 billion cubic meters/year by the turn of the century. The operating activities of the two leading participants, SNAM and AGIP, in Italy's natural gas industry are highlighted. Specific problems which contribute to the high operating costs of natural gas storage are identified and a review is made of national normatives governing gas storage. The report comes complete with a glossary of the relative terminology and units of measure

  7. Anthology of dry storage solutions

    Energy Technology Data Exchange (ETDEWEB)

    Allimann, Nathalie; Otton, Camille [AREVA, Paris (France)

    2012-03-15

    Around 35,000 PWR, BWR or Veer used fuel elements with various enrichment value up to 5%, various cooling time down to 2 years and various burn-ups up to 60,000 Mwd/tU are currently stored in AREVA dry storage solutions. These solutions are delivered in the United States, in Japan and in many European countries like Belgium, Switzerland, Italy, Armenia and Germany. With more than 1000 dry storage solutions delivered all over the world AREVA is the leader on this market. Dealing with dry storage is not an easy task. Products have to be flexible, to be adapted to customer needs and to the national regulations which may stipulate very strict tests such as airplane crash or simulation of earthquake. To develop a dry storage solution for a foreign country means to deal with its national competent authorities. All the national competent authorities do not have the same requirements. Storage conditions may also be different.

  8. Anthology of dry storage solutions

    International Nuclear Information System (INIS)

    Allimann, Nathalie; Otton, Camille

    2012-01-01

    Around 35,000 PWR, BWR or Veer used fuel elements with various enrichment value up to 5%, various cooling time down to 2 years and various burn-ups up to 60,000 Mwd/tU are currently stored in AREVA dry storage solutions. These solutions are delivered in the United States, in Japan and in many European countries like Belgium, Switzerland, Italy, Armenia and Germany. With more than 1000 dry storage solutions delivered all over the world AREVA is the leader on this market. Dealing with dry storage is not an easy task. Products have to be flexible, to be adapted to customer needs and to the national regulations which may stipulate very strict tests such as airplane crash or simulation of earthquake. To develop a dry storage solution for a foreign country means to deal with its national competent authorities. All the national competent authorities do not have the same requirements. Storage conditions may also be different

  9. 100-N Area underground storage tank closures

    Energy Technology Data Exchange (ETDEWEB)

    Rowley, C.A.

    1993-08-01

    This report describes the removal/characterization actions concerning underground storage tanks (UST) at the 100-N Area. Included are 105-N-LFT, 182-N-1-DT, 182-N-2-DT, 182-N-3-DT, 100-N-SS-27, and 100-N-SS-28. The text of this report gives a summary of remedial activities. In addition, correspondence relating to UST closures can be found in Appendix B. Appendix C contains copies of Unusual Occurrence Reports, and validated sampling data results comprise Appendix D.

  10. 100-N Area underground storage tank closures

    International Nuclear Information System (INIS)

    Rowley, C.A.

    1993-01-01

    This report describes the removal/characterization actions concerning underground storage tanks (UST) at the 100-N Area. Included are 105-N-LFT, 182-N-1-DT, 182-N-2-DT, 182-N-3-DT, 100-N-SS-27, and 100-N-SS-28. The text of this report gives a summary of remedial activities. In addition, correspondence relating to UST closures can be found in Appendix B. Appendix C contains copies of Unusual Occurrence Reports, and validated sampling data results comprise Appendix D

  11. 200 Area plateau inactive miscellaneous underground storage tanks locations

    International Nuclear Information System (INIS)

    Brevick, C.H.

    1997-01-01

    Fluor Daniel Northwest (FDNW) has been tasked by Lockheed Martin Hanford Corporation (LMHC) to incorporate current location data for 64 of the 200-Area plateau inactive miscellaneous underground storage tanks (IMUST) into the centralized mapping computer database for the Hanford facilities. The IMUST coordinate locations and tank names for the tanks currently assigned to the Hanford Site contractors are listed in Appendix A. The IMUST are inactive tanks installed in underground vaults or buried directly in the ground within the 200-East and 200-West Areas of the Hanford Site. The tanks are categorized as tanks with a capacity of less than 190,000 liters (50,000 gal). Some of the IMUST have been stabilized, pumped dry, filled with grout, or may contain an inventory or radioactive and/or hazardous materials. The IMUST have been out of service for at least 12 years

  12. Dry storage of Magnox fuel

    International Nuclear Information System (INIS)

    1986-09-01

    This work, commissioned by the CEGB, studies the feasibility of a combination of short-term pond storage and long-term dry storage of Magnox spent fuel as a cheaper alternative to reprocessing. Storage would be either at the reactor site or a central site. Two designs are considered, based on existing design work done by GEC-ESL and NNC; the capsule design developed by NNC and with storage in passive vaults for up to 100 yrs and the GEC-ESL tube design developed at Wylfa for the interim storage of LWR. For the long-term storage of Magnox spent fuel the GEC-ESL tubed vault all-dry storage method is recommended and specifications for this method are given. (U.K.)

  13. An Underground Storage Tank Integrated Demonstration report

    International Nuclear Information System (INIS)

    Quadrel, M.J.; Hunter, V.L.; Young, J.K.; Lini, D.C.; Goldberg, C.

    1993-04-01

    The Waste Characterization Data and Technology Development Needs Assessment provides direct support to the Underground Storage Tank Integrated Demonstration (UST-ID). Key users of the study's products may also include individuals and programs within the US Department of Energy (DOE) Office of Technology Development (EM-50), the Office of Waste Operations (EM-30), and the Office of Environmental Restoration (EM-40). The goal of this work is to provide the UST-ID with a procedure for allocating funds across competing characterization technologies in a timely and defensible manner. It resulted in three primary products: 1. It organizes and summarizes information on underground storage tank characterization data needs. 2. It describes current technology development activity related to each need and flags areas where technology development may be beneficial. 3. It presents a decision process, with supporting software, for evaluating, prioritizing, and integrating possible technology development funding packages. The data presented in this document can be readily updated as the needs of the Waste Operations and Environmental Restoration programs mature and as new and promising technology development options emerge

  14. Dry spent fuel storage licensing

    International Nuclear Information System (INIS)

    Sturz, F.C.

    1995-01-01

    In the US, at-reactor-site dry spent fuel storage in independent spent fuel storage installations (ISFSI) has become the principal option for utilities needing storage capacity outside of the reactor spent fuel pools. Delays in the geologic repository operational date at or beyond 2010, and the increasing uncertainty of the US Department of Energy's (DOE) being able to site and license a Monitored Retrievable Storage (MRS) facility by 1998 make at-reactor-site dry storage of spent nuclear fuel increasingly desirable to utilities and DOE to meet the need for additional spent fuel storage capacity until disposal, in a repository, is available. The past year has been another busy year for dry spent fuel storage licensing. The licensing staff has been reviewing 7 applications and 12 amendment requests, as well as participating in inspection-related activities. The authors have licensed, on a site-specific basis, a variety of dry technologies (cask, module, and vault). By using certified designs, site-specific licensing is no longer required. Another new cask has been certified. They have received one new application for cask certification and two amendments to a certified cask design. As they stand on the brink of receiving multiple applications from DOE for the MPC, they are preparing to meet the needs of this national program. With the range of technical and licensing options available to utilities, the authors believe that utilities can meet their need for additional spent fuel storage capacity for essentially all reactor sites through the next decade

  15. Permanent Closure of the TAN-664 Underground Storage Tank

    Energy Technology Data Exchange (ETDEWEB)

    Bradley K. Griffith

    2011-12-01

    This closure package documents the site assessment and permanent closure of the TAN-664 gasoline underground storage tank in accordance with the regulatory requirements established in 40 CFR 280.71, 'Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.'

  16. Underground Gas Storage in the World 2013 (fifth edition)

    International Nuclear Information System (INIS)

    Cornot-Gandolphe, Sylvie

    2013-06-01

    Since its first publication in 1990, 'Underground Gas Storage in the World' has been the industry's reference on underground gas storage (UGS). The updated 2013 edition includes in-depth CEDIGAZ's analyses of the latest developments and trends in the storage industry all over the world as well as extensive country analyses with complete datasets including current, under construction and planned Underground Gas Storage facilities in 48 countries. It describes the 688 existing storage facilities in the world and the 236 projects under construction and planned. Future storage demand and its main drivers are presented at global and regional levels. The study builds on the CEDIGAZ Underground Gas Storage Database, the only worldwide Underground Gas Storage database to be updated every year. This document summarizes the key findings of the Survey which includes four main parts: The first part gives an overview of underground gas storage in the world at the beginning of 2013 and analyzes future storage needs by 2030, at regional and international levels. The second part focuses on new trends and issues emerging or developing in key storage markets. It analyzes the emerging storage market in China, reviews the storage business climate in Europe, examines Gazprom's storage strategy in Europe, and reviews recent trends in storage development in the United States. The third part gives some fundamental background on technical, economic and regulatory aspects of gas storage. The fourth part gives a countrywide analysis of the 48 countries in the world holding underground gas storage facilities or planning storage projects. 48 countries are surveyed with 688 existing UGS facilities, 256 projects under construction or planned

  17. Underground storage tanks containing hazardous chemicals

    International Nuclear Information System (INIS)

    Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.; Hillger, R.W.; Tafuri, A.N.

    1991-01-01

    The regulations issued by the United States Environmental Protection Agency in 1988 require, with several exceptions, that underground storage tank systems containing petroleum fuels and hazardous chemicals be routinely tested for releases. This paper summarizes the release detection regulations for tank systems containing chemicals and gives a preliminary assessment of the approaches to release detection currently being used. To make this assessment, detailed discussions were conducted with providers and manufacturers of leak detection equipment and testing services, owners or operators of different types of chemical storage tank systems, and state and local regulators. While these discussions were limited to a small percentage of each type of organization, certain observations are sufficiently distinctive and important that they are reported for further investigation and evaluation. To make it clearer why certain approaches are being used, this paper also summarizes the types of chemicals being stored, the effectiveness of several leak detection testing systems, and the number and characteristics of the tank systems being used to store these products

  18. Underground Storage Alternative To Nigeria's Gas Flaring

    International Nuclear Information System (INIS)

    Obi, A.I

    2004-01-01

    Energy demands are increasing as the world's population of energy users grows. At the same time many nations want to decommission nuclear plants in support of a cleaner environment. Clean burning natural gas is the fuel most likely to meet society's complex requirements. Demand for natural gas will rise more strongly than for any fossil fuel. The utilization of the huge gas resources form the petroleum deposit in the Niger Delta area is the major problem confronting the oil/gas industry in Nigeria and the disposal of associated gas has been a major challenge for the barrel of oil; hence with oil production of about 2.0 million barrels per day, some 2.0 billion standard cubic feet of AG is producing everyday. An alarming proportion of the gas is wasted by flaring, while very small proportion is used by oil-producing companies and other most alarming rate of flaring in the world compared with other oil/gas producing countries. This paper highlights the numerous benefits accruing from proper utilization of natural gas using SASOL of South Africa as an example and recommends underground storage of natural gas as an industry that will help check flaring, meet fluctuating demand and create wealth for the nation

  19. Acoustic imaging of underground storage tank wastes

    International Nuclear Information System (INIS)

    Mech, S.J.

    1995-09-01

    Acoustics is a potential tool to determine the properties of high level wastes stored in Underground Storage Tanks. Some acoustic properties were successfully measured by a limited demonstration conducted in 114-TX. This accomplishment provides the basis for expanded efforts to qualify techniques which depend on the acoustic properties of tank wastes. This work is being sponsored by the Department of Energy under the Office of Science and Technology. In FY-1994, limited Tank Waste Remediation Systems EM-30 support was available at Hanford and Los Alamos National Laboratory. The Massachusetts Institute of Technology (MIT) and Earth Resources Laboratory (ERL) were engaged for analysis support, and Elohi Geophysics, Inc. for seismic testing services. Westinghouse-Hanford Company provided the testing and training, supplied the special engineering and safety analysis equipment and procedures, and provided the trained operators for the actual tank operations. On 11/9/94, limited in-tank tests were successfully conducted in tank 114-TX. This stabilized Single Shell Tank was reported as containing 16.8 feet of waste, the lower 6.28 feet of which contained interstitial liquid. Testing was conducted over the lower 12 feet, between two Liquid Observation Wells thirty feet apart. The ''quick-look'' data was reviewed on-site by MIT and Elohi

  20. Remote inspection of underground storage tanks

    International Nuclear Information System (INIS)

    Griebenow, B.L.; Martinson, L.M.

    1992-01-01

    Westinghouse Idaho Nuclear Company, Inc. (WINCO) operates the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy. The ICPP's mission is to process government-owned spent nuclear fuel. The process involves dissolving the fuel, extracting off uranium, and calcining the waste to a solid form for storage, Prior to calcining, WINCO temporarily stores the liquid waste from this process in eleven 1,135,600-l(300,000-gal), 15,2-m (50-ft)-diam, high-level liquid waste tanks. Each of these stainless steel tanks is contained within an underground concrete vault. The only access to the interior of the tanks is through risers that extend from ground level to the dome of the tanks. WINCO is replacing these tanks because of their age and the fact that they do not meet all of the current design requirements. The tanks will be replaced in two phases. WINCO is now in the Title I design stage for four new tank and vault systems to replace five of the existing systems. The integrity of the six remaining tanks must be verified to continue their use until they can be replaced in the second phase. To perform any integrity analysis, the inner surface of the tanks must be inspected. The remote tank inspection (RTI) robotic system, designed by RedZone Robotics of Pittsburgh, Pennsylvania, was developed to access the interior of the tanks and position various end effectors required to perform tank wall inspections

  1. 30 CFR 75.1903 - Underground diesel fuel storage facilities and areas; construction and safety precautions.

    Science.gov (United States)

    2010-07-01

    ... areas; construction and safety precautions. 75.1903 Section 75.1903 Mineral Resources MINE SAFETY AND...; construction and safety precautions. (a) Permanent underground diesel fuel storage facilities must be— (1... with at least 240 pounds of rock dust and provided with two portable multipurpose dry chemical type...

  2. Underground storage touted as CO2 solution

    International Nuclear Information System (INIS)

    Kishewitsch, S.

    2000-01-01

    As power generating companies weigh the merits of switching from coal to natural gas in order to reduce carbon dioxide emissions into the atmosphere, energy analysts predict that coal will remain a major contributor to world energy supplies well into the 21st century. For example, the Electric Power Institute estimates that a new 1,000 MW power plant need to be built somewhere in the world every two days for the next fifty years to meet the global demand for energy, and that in major emerging economies such as India and China, many of those plants will be fueled by coal. Various methods already are being tried to safely contain the carbon dioxide resulting from this vastly carbon-intensive economy. One of the more promising approaches involves burying the gas deep in the ground where it will stay safely for hundreds, if not thousands of years. Burial underground may take the form of burial in deep exhausted oil or gas formations, or burial in the deep ocean. Injection into exhausted oil and gas formations is favoured because of the ready availability of thousands of gigatonnes of underground formations and because of the extensive knowledge base already in existence regarding the size and geological properties of oil and gas reservoirs and the behaviour of carbon dioxide under these conditions. Injecting carbon dioxide into unmineable coal seams could replace methane bound to the coal; it is already being done in Alberta as one of the two pilot projects in North America, the other being in Mexico. Carbon dioxide injection to stimulate enhanced oil recovery is also being experimented with, among others by PanCanadian Resources Ltd at its Weyburn reservoir in Saskatchewan. Injection into salt domes and deep saline aquifers is another alternative. Sequestration in the ocean in a variety of forms is also the subject of several experiments. To illustrate the attractiveness of deep ocean storage, it is stated that the ocean contains at least 50 times more carbon than the

  3. Underground gas storage in the World - 2013 (fifth Edition)

    International Nuclear Information System (INIS)

    Cornot-Gandolphe, Sylvie

    2013-07-01

    Since its first publication in 1990, 'Underground Gas Storage in the World' has been the industry's reference on underground gas storage (UGS). The updated 2013 edition includes in-depth CEDIGAZ's analyses of the latest developments and trends in the storage industry all over the world as well as extensive country analyses with complete datasets including current, under construction and planned Underground Gas Storage facilities in 48 countries. It describes the 688 existing storage facilities in the world and the 236 projects under construction and planned. Future storage demand and its main drivers are presented at global and regional levels. 'Underground Gas Storage in the World 2013' builds on the CEDIGAZ Underground Gas Storage Database, the only worldwide Underground Gas Storage database to be updated every year. The Survey includes four main parts: The first part gives an overview of underground gas storage in the world at the beginning of 2013 and analyzes future storage needs by 2030, at regional and international levels. The second part focuses on new trends and issues emerging or developing in key storage markets. It analyzes the emerging storage market in China, reviews the storage business climate in Europe, examines Gazprom's storage strategy in Europe, and reviews recent trends in storage development in the United States. The third part gives some fundamental background on technical, economic and regulatory aspects of gas storage. The fourth part gives a countrywide analysis of the 48 countries in the world holding underground gas storage facilities or planning storage projects. 48 countries surveyed, 688 existing UGS facilities, 256 projects under construction or planned. The document includes 70 tables, 72 charts and figures, 44 country maps. The countries surveyed are: Europe : Albania, Austria, Belgium, Bosnia, Bulgaria, Croatia, Czech Republic, Denmark, France, Germany, Greece, Hungary, Ireland, Italy, Latvia, Lithuania, Netherlands, Poland

  4. Viewing Systems for Large Underground Storage Tanks

    International Nuclear Information System (INIS)

    Heckendorn, F.M.; Robinson, C.W.; Anderson, E.K.; Pardini, A.F.

    1996-01-01

    Specialized remote video systems have been successfully developed and deployed in a number of large radiological Underground Storage Tanks (USTs)that tolerate the hostile tank interior, while providing high resolution video to a remotely located operator. The deployment is through 100 mm (4 in) tank openings, while incorporating full video functions of the camera, lights, and zoom lens. The usage of remote video minimizes the potential for personnel exposure to radiological and hazardous conditions, and maximizes the quality of the visual data used to assess the interior conditions of both tank and contents. The robustness of this type of remote system has a direct effect on the potential for radiological exposure that personnel may encounter. The USTs typical of the Savannah River and Hanford Department Of Energy - (DOE) sites are typically 4.5 million liter (1.2 million gal) units under earth. or concrete overburden with limited openings to the surface. The interior is both highly contaminated and radioactive with a wide variety of nuclear processing waste material. Some of the tanks are -flammable rated -to Class 1, Division 1,and personnel presence at or near the openings should be minimized. The interior of these USTs must be assessed periodically as part of the ongoing management of the tanks and as a step towards tank remediation. The systems are unique in their deployment technology, which virtually eliminates the potential for entrapment in a tank, and their ability to withstand flammable environments. A multiplicity of components used within a common packaging allow for cost effective and appropriate levels of technology, with radiation hardened components on some units and lesser requirements on other units. All units are completely self contained for video, zoom lens, lighting, deployment,as well as being self purging, and modular in construction

  5. The subtle attractions of dry vault storage

    International Nuclear Information System (INIS)

    Ealing, C.J.

    1993-01-01

    Utilities in the United States of America, Scotland and Hungary have all adopted dry vault technology in their plans for spent fuel storage. This article looks at what makes dry storage an attractive option. (author)

  6. The underground storages of carbon dioxide. Juridical aspects

    International Nuclear Information System (INIS)

    Bersani, F.

    2006-04-01

    In the framework of the reduction of the carbon dioxide emissions in the air, the underground storage of the CO 2 is studied. Some experimentation are already realized in the world and envisaged in France. This document aims to study the juridical aspects of these first works in France. After a presentation of the realization conditions and some recalls on the carbon dioxide its capture and storage, the natural CO 2 underground storages and the first artificial storages are discussed. The CO 2 waste qualification, in the framework of the environmental legislation is then detailed with a special task on the Lacq region. The problem of the sea underground storages is also presented. (A.L.B.)

  7. Aims, organization and activities of the consortium for underground storage

    International Nuclear Information System (INIS)

    Stucky, G.

    1977-01-01

    The consortium of Swiss authorities interested in underground storage (the petroleum oil and gas industries, for fuel storage; the nuclear industry for radioactive waste disposal), was initiated in 1972. The author outlines the motives behind the formation of the consortium and outlines its structure and objectives. The envisaged projects are outlined. (F.Q.)

  8. Natural convection and vapor loss during underground waste storage

    International Nuclear Information System (INIS)

    Plys, M.G.; Epstein, M.; Turner, D.

    1996-01-01

    Natural convection and vapor loss from underground waste storage tanks is examined here. Stability criteria are provided for the onset of natural convection flow within the headspace of a tank, and between tanks and the environment. The flowrate is quantified and used to predict vapor losses during storage

  9. Decision analysis of Hanford underground storage tank waste retrieval systems

    International Nuclear Information System (INIS)

    Merkhofer, M.W.; Bitz, D.A.; Berry, D.L.; Jardine, L.J.

    1994-05-01

    A decision analysis approach has been proposed for planning the retrieval of hazardous, radioactive, and mixed wastes from underground storage tanks. This paper describes the proposed approach and illustrates its application to the single-shell storage tanks (SSTs) at Hanford, Washington

  10. Dry storage of spent fuel

    International Nuclear Information System (INIS)

    Jeffrey, R.

    1993-01-01

    Scottish Nuclear's plans to build and operate dry storage facilities at each of its two nuclear power station sites in Scotland are explained. An outline of where waste materials arise as part of the operation and decommissioning of nuclear power stations, the volumes for each category of high-, intermediate-and low-level wastes and the costs involved are given. The present procedure for the spent fuels from Hunterston-B and Torness stations is described and Scottish Nuclear's aims of driving output up and costs down are studied. (UK)

  11. Regulatory approaches to hydrocarbon contamination from underground storage tanks

    International Nuclear Information System (INIS)

    Daugherty, S.J.

    1991-01-01

    Action or lack of action by the appropriate regulatory agency is often the most important factor in determining remedial action or closure requirements for hydrocarbon contaminated sites. This paper reports that the diversity of regulatory criteria is well known statewide and well documented nationally. In California, the diversity of approaches is due to: that very lack of a clear understanding of the true impact of hydrocarbon contamination: lack of state or federal standards for soil cleanup, and state water quality objectives that are not always achievable; vagueness in the underground storage tank law; and the number and diversity of agencies enforcing the underground storage tank regulations

  12. The prospects for dry fuel storage

    International Nuclear Information System (INIS)

    Harris, G.G.; Elliott, D.

    1994-01-01

    Dry storage of spent nuclear fuels is one method of dealing with radioactive waste. This article reports from a one day seminar on future prospects for dry fuel storage held in November 1993. Dry storage in an inert gas or air environment in vaults or casks, is an alternative to wet storage in water-filled ponds. Both wet and dry storage form part of the Interim Storage option for radioactive waste materials, and form alternatives to reprocessing or direct disposal in a deep repository. It has become clear that a large market for dry fuel storage will exist in the future. It will therefore be necessary to ensure that the various technical, safety, commercial, legislative and political constraints associated with it can be met effectively. (UK)

  13. Does underground storage still require sophisticated studies?

    International Nuclear Information System (INIS)

    Marsily, G. de

    1997-01-01

    Most countries agree to the necessity of burying high or medium-level wastes in geological layers situated at a few hundred meters below the ground level. The advantages and disadvantages of different types of rock such as salt, clay, granite and volcanic material are examined. Sophisticated studies are lead to determine the best geological confinement but questions arise about the time for which safety must be ensured. France has chosen 3 possible sites. These sites are geologically described in the article. The final place will be proposed after a testing phase of about 5 years in an underground facility. (A.C.)

  14. Developing new transportable storage casks for interim dry storage

    International Nuclear Information System (INIS)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R.

    2004-01-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication

  15. Development of spent fuel dry storage technology

    International Nuclear Information System (INIS)

    Maruoka, Kunio; Matsunaga, Kenichi; Kunishima, Shigeru

    2000-01-01

    The spent fuels are the recycle fuel resources, and it is very important to store the spent fuels in safety. There are two types of the spent fuel interim storage system. One is wet storage system and another is dry storage system. In this study, the dry storage technology, dual purpose metal cask storage and canister storage, has been developed. For the dual purpose metal cask storage, boronated aluminum basket cell, rational cask body shape and shaping process have been developed, and new type dual purpose metal cask has been designed. For the canister storage, new type concrete cask and high density vault storage technology have been developed. The results of this study will be useful for the spent fuel interim storage. Safety and economical spent fuel interim storage will be realized in the near future. (author)

  16. Underground gas storage in the World - Cedigaz survey

    International Nuclear Information System (INIS)

    Benquey, R.

    2010-01-01

    The 2010 edition of 'Underground Gas Storage in the World' provides an update to the previous survey released by CEDIGAZ in 2006. At that time, 610 underground gas storage (UGS) facilities were in operation worldwide, with a working capacity of 319 billion cubic metres (bcm). As of 1 January 2010, this number had reached 642 facilities with a working gas capacity of 333 bcm, or 10.8% of world gas consumption. By 2020, the global UGS demand is expected to grow at a pace of 3.3% per year, and according to the projects identified, more than 760 UGS sites could be active in the world with a total working capacity of approximately 465 bcm. In this survey, CEDIGAZ analyses the following trends which characterise the rapid development of underground gas storage in the world: - the strong dynamics of the European storage market, where 127 projects could add 75 bcm of working capacity by 2020, - the continued development of the UGS market in the United States (49 projects), encouraged by market-based rates allowed by the FERC, and rapid permitting processes, - the development of facilities in countries with little or no storage capacities at present, in Asia/Oceania, the C.I.S., and Eastern Europe in particular. This survey provides an analysis of the recent evolutions in the technic-economic aspects of the underground gas storage business, as well as an overview of the UGS markets and their developments in the world, country by country. A specific section is dedicated to the analysis of future UGS needs in Europe by 2020: - Technic-economic aspects of UGS: This part of the survey analyses the latest technical improvements and research axes in the field of underground gas storage. As it is more difficult to build greenfield storage facilities, a lot of work has been done to improve the performance and flexibility of existing storage sites. This section also deals with the evolution of investment and operational costs in storage over the last few years. Furthermore, the

  17. Numerical modeling of underground storage system for natural gas

    Science.gov (United States)

    Ding, J.; Wang, S.

    2017-12-01

    Natural gas is an important type of base-load energy, and its supply needs to be adjusted according to different demands in different seasons. For example, since natural gas is increasingly used to replace coal for winter heating, the demand for natural gas in winter is much higher than that in other seasons. As storage systems are the essential tools for balancing seasonal supply and demand, the design and simulation of natural gas storage systems form an important research direction. In this study, a large-scale underground storage system for natural gas is simulated based on theoretical analysis and finite element modeling.It is proven that the problem of axi-symmetric Darcy porous flow of ideal gas is governed by the Boussinesq equation. In terms of the exact solution to the Boussinesq equation, the basic operating characteristics of the underground storage system is analyzed, and it is demonstrated that the propagation distance of the pore pressure is proportional to the 1/4 power of the mass flow rate and to the 1/2 power of the propagation time. This quantitative relationship can be used to guide the overall design of natural gas underground storage systems.In order to fully capture the two-way coupling between pore pressure and elastic matrix deformation, a poro-elastic finite element model for natural gas storage is developed. Based on the numerical model, the dynamic processes of gas injection, storage and extraction are simulated, and the corresponding time-dependent surface deformations are obtained. The modeling results not only provide a theoretical basis for real-time monitoring for the operating status of the underground storage system through surface deformation measurements, but also demonstrate that a year-round balance can be achieved through periodic gas injection and extraction.This work is supported by the CAS "100 talents" Program and the National Natural Science Foundation of China (41371090).

  18. VOLUMETRIC LEAK DETECTION IN LARGE UNDERGROUND STORAGE TANKS - VOLUME I

    Science.gov (United States)

    A set of experiments was conducted to determine whether volumetric leak detection system presently used to test underground storage tanks (USTs) up to 38,000 L (10,000 gal) in capacity could meet EPA's regulatory standards for tank tightness and automatic tank gauging systems whe...

  19. Arrangement for underground storage of materials of every kind

    International Nuclear Information System (INIS)

    Marek, O.; Seisenbacher, H.; Toth, L.

    1982-01-01

    Construction of a spheroidal tank, made of two sheets of concrete, used for underground storage. Space between inner and outer sheet is filled with a vibration absorbing material. The bottom of the outer sheet is made of material with lower rigidness, which allows the line of fault in cases of tectonic motions to slide off. (J.K.) [de

  20. Underground storage tanks cause environmental chaos

    International Nuclear Information System (INIS)

    Cruver, P.C.

    1991-01-01

    This paper reports that during the 1950s and the subsequent three decades, petroleum products were stored in single-walled steel underground tanks; an out-of-sight, out-of-mind philosophy prevailed. Unfathomable amounts of toxic petroleum products leaking into the nation's ground water supplies has prompted enactment of recent and much needed legislation and regulation to remedy this major problem. Is the public aware of this serious ecological imbroglio? No, not as yet; except for the closing of many rural service stations and the plethora of dug-up, exposed tanks at urban stations, one could never imagine the severity of this debacle confronting the petroleum industry and the nation's environment

  1. Underground or aboveground storage tanks - A critical decision

    International Nuclear Information System (INIS)

    Rizzo, J.A.

    1992-01-01

    With the 1988 promulgation of the comprehensive Resource Conservation and Recovery Act (RCRA) regulations for underground storage of petroleum and hazardous substances, many existing underground storage tank (UST) owners have been considering making the move to aboveground storage. While on the surface, this may appear to be the cure-all to avoiding the underground leakage dilemma, there are many other new and different issues to consider with aboveground storage. The greatest misconception is that by storing materials above ground, there is no risk of subsurface environmental problems. It should be noted that with the aboveground storage tank (AGST) systems, there is still considerable risk of environmental contamination, either by the failure of onground tank bottoms or the spillage of product onto the ground surface where it subsequently finds its way to the ground water. In addition, there are added safety concerns that must be addressed. The greatest interest in AGSTs comes from managers with small volumes of used oil, fresh oil, solvents, chemicals, or heating oil. Dealing with small capacity tanks is not so different than large bulk storage - and, in fact, it lends itself to more options, such as portable storage, tank within tank configurations and inside installations. So what are the other specific areas of concern besides environmental to be addressed when making the decision between underground and aboveground tanks? The primary issues that will be addressed in this presentation are: (1) safety; (2) product losses; (3) cost comparison of USTs vs AGSTs; (4) space availability/accessibility; (5) precipitation handling; (6) aesthetics and security; (7) pending and existing regulations

  2. Interim dry fuel storage for magnox reactors

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, N [National Nuclear Corporation, Risley, Warrington (United Kingdom); Ealing, C [GEC Energy Systems Ltd, Whetstone, Leicester (United Kingdom)

    1985-07-01

    In the UK the practice of short term buffer storage in water ponds prior to chemical reprocessing had already been established on the early gas cooled reactors in Calder Hall. Thus the choice of water pond buffer storage for MGR power plants logically followed the national policy decision to reprocess. The majority of the buffer storage period would take place at the reprocessing plant with only a nominal of 100 days targeted at the station. Since Magnox clad fuel is not suitable for long term pond storage, alternative methods of storage on future stations was considered desirable. In addition to safeguards considerations the economic aspects of the fuel cycle has influenced the conclusion that today the purchase of a MGR power plant with dry spent fuel storage and without commitment to reprocess would be a rational decision for a country initiating a nuclear programme. Dry storage requirements are discussed and two designs of dry storage facilities presented together with a fuel preparation facility.

  3. Interim dry fuel storage for magnox reactors

    International Nuclear Information System (INIS)

    Bradley, N.; Ealing, C.

    1985-01-01

    In the UK the practice of short term buffer storage in water ponds prior to chemical reprocessing had already been established on the early gas cooled reactors in Calder Hall. Thus the choice of water pond buffer storage for MGR power plants logically followed the national policy decision to reprocess. The majority of the buffer storage period would take place at the reprocessing plant with only a nominal of 100 days targeted at the station. Since Magnox clad fuel is not suitable for long term pond storage, alternative methods of storage on future stations was considered desirable. In addition to safeguards considerations the economic aspects of the fuel cycle has influenced the conclusion that today the purchase of a MGR power plant with dry spent fuel storage and without commitment to reprocess would be a rational decision for a country initiating a nuclear programme. Dry storage requirements are discussed and two designs of dry storage facilities presented together with a fuel preparation facility

  4. Silos. Optimisation of underground storages' management

    International Nuclear Information System (INIS)

    Formaggio, M.

    1997-01-01

    The operation of Silos in the optimization of storages' management at Snam is presented, together with an assessment of the benefits obtained through closer attention and higher commitment of the staff, as well as better communication between Dispatching and other organizational functions. Silos has proven to be a useful decision-making tool, while applying traditional risk-assessment methods. (au)

  5. High temperature underground thermal energy storage system for solar energy

    Science.gov (United States)

    Collins, R. E.

    1980-01-01

    The activities feasibility of high temperature underground thermal storage of energy was investigated. Results indicate that salt cavern storage of hot oil is both technically and economically feasible as a method of storing huge quantities of heat at relatively low cost. One particular system identified utilizes a gravel filled cavern leached within a salt dome. Thermal losses are shown to be less than one percent of cyclically transferred heat. A system like this having a 40 MW sub t transfer rate capability and over eight hours of storage capacity is shown to cost about $13.50 per KWh sub t.

  6. Dry well storage of spent LWBR fuel

    International Nuclear Information System (INIS)

    Christensen, A.B.; Fielding, K.D.

    1985-01-01

    Recently, 50 dry wells were constructed at the Idaho Chemical Processing Plant (ICPP) to temporarily store the Light Water Breeder Reactor (LWBR) fuel. Over 400 dry wells of the same design are projected to be constructed in the next 5 yr at the ICPP to store unreprocessible fuels until a permanent repository becomes available. This summary describes the LWBR fuel storage dry wells and the enhancements made over the Peach Bottom fuel and Fermi blanket dry wells that have been in use for up to 4 yr. Dry well storage at the ICPP has historically been found to be a safe and efficient method of temporary fuel storage. The LWBR dry wells should be more reliable than the original dry wells and provide data not previously available

  7. From clay bricks to deep underground storage

    International Nuclear Information System (INIS)

    2012-05-01

    This booklet issued by the Swiss National Cooperative for the Disposal of Radioactive Waste NAGRA takes a look at the use of clay strata for the storage of radioactive wastes in deep-lying repositories. First of all, a geological foray is made concerning the history of the use of clay and its multifarious uses. The characteristics of clay and its composition are examined and its formation in the geological past is explained. In particular Opalinus clay is looked at and the structures to be found are discussed. The clay's various properties and industrial uses are examined and its sealing properties are examined. Also, Bentonite clay is mentioned and work done by Nagra and co-researchers is noted

  8. Salt creep design consideration for underground nuclear waste storage

    International Nuclear Information System (INIS)

    Li, W.T.; Wu, C.L.; Antonas, N.J.

    1983-01-01

    This paper summarizes the creep consideration in the design of nuclear waste storage facilities in salt, describes the non-linear analysis method for evaluating the design adequacy, and presents computational results for the current storage design. The application of rock mechanics instrumentation to assure the appropriateness of the design is discussed. It also describes the design evolution of such a facility, starting from the conceptual design, through the preliminary design, to the detailed design stage. The empirical design method, laboratory tests and numerical analyses, and the underground in situ tests have been incorporated in the design process to assure the stability of the underground openings, retrievability of waste during the operation phase and encapsulation of waste after decommissioning

  9. Indian Country Leaking Underground Storage Tanks, Region 9, 2016

    Science.gov (United States)

    This GIS dataset contains point features that represent Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. This dataset contains facility name and locational information, status of LUST case, operating status of facility, inspection dates, and links to No Further Action letters for closed LUST cases. This database contains 1230 features, with 289 features having a LUST status of open, closed with no residual contamination, or closed with residual contamination.

  10. Polymers for subterranean containment barriers for underground storage tanks (USTs)

    International Nuclear Information System (INIS)

    Heiser, J.H.; Colombo, P.; Clinton, J.

    1992-12-01

    The US Department of Energy (DOE) set up the Underground Storage Tank Integrated Demonstration Program (USTID) to demonstrate technologies for the retrieval and treatment of tank waste, and closure of underground storage tanks (USTs). There are more than 250 underground storage tanks throughout the DOE complex. These tanks contain a wide variety of wastes including high level, low level, transuranic, mixed and hazardous wastes. Many of the tanks have performed beyond the designed lifetime resulting in leakage and contamination of the local geologic media and groundwater. To mitigate this problem it has been proposed that an interim subterranean containment barrier be placed around the tanks. This would minimize or prevent future contamination of soil and groundwater in the event that further tank leakages occur before or during remediation. Use of interim subterranean barriers can also provide sufficient time to evaluate and select appropriate remediation alternatives. The DOE Hanford site was chosen as the demonstration site for containment barrier technologies. A panel of experts for the USTID was convened in February, 1992, to identify technologies for placement of subterranean barriers. The selection was based on the ability of candidate grouts to withstand high radiation doses, high temperatures and aggressive tank waste leachates. The group identified and ranked nine grouting technologies that have potential to place vertical barriers and five for horizontal barriers around the tank. The panel also endorsed placement technologies that require minimal excavation of soil surrounding the tanks

  11. Spent fuel storage - dry storage options and issues

    International Nuclear Information System (INIS)

    Akins, M.J.

    2007-01-01

    The increase in the number of nuclear energy power generation facilities will require the ability to store the spent nuclear fuel for a long period until the host countries develop reprocessing or disposal options. Plants have storage pools which are closely associated with the operating units. These are excellent for short term storage, but require active maintenance and operations support which are not desirable for the long term. Over the past 25 years, dry storage options have been developed and implemented throughout the world. In recent years, protection against terrorist attack has become an increasing source of design objectives for these facilities, as well as the main nuclear plant. This paper explores the current design options of dry storage cask systems and examines some of the current design issues for above ground , in-ground, or below-ground storage of spent fuel in dry casks. (author)

  12. Developing new transportable storage casks for interim dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

    2004-07-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication.

  13. Model based, sensor-directed remediation of underground storage tanks

    International Nuclear Information System (INIS)

    Harrigan, R.W.; Thunborg, S.

    1990-01-01

    Sensor-rich, intelligent robots that function with respect to models of their environment have significant potential to reduce the time and cost for the cleanup of hazardous waste while increasing operator safety. Sandia National Laboratories (SNL) is performing technology development and experimental investigations into the application of intelligent robot control technology to the problem of cleaning up waste stored in underground tanks. The tasks addressed in the SNL experiments are in situ physical characterizations of underground storage tanks (USTs) as well as the contained waste and the removal of the waste from the tank both for laboratory analysis and as part of the tank cleanup process. Both fully automatic and manual robot control technologies are being developed and demonstrated. The SNL-developed concept of human-assisted computer control will be employed whenever manual control of the robot is required. The UST Robot Technology Development Laboratory (URTDL) consists of a commercial gantry robot modified to allow hybrid force/position control

  14. Performance Analysis of Depleted Oil Reservoirs for Underground Gas Storage

    Directory of Open Access Journals (Sweden)

    Dr. C.I.C. Anyadiegwu

    2014-02-01

    Full Text Available The performance of underground gas storage in depleted oil reservoir was analysed with reservoir Y-19, a depleted oil reservoir in Southern region of the Niger Delta. Information on the geologic and production history of the reservoir were obtained from the available field data of the reservoir. The verification of inventory was done to establish the storage capacity of the reservoir. The plot of the well flowing pressure (Pwf against the flow rate (Q, gives the deliverability of the reservoir at various pressures. Results of the estimated properties signified that reservoir Y-19 is a good candidate due to its storage capacity and its flow rate (Q of 287.61 MMscf/d at a flowing pressure of 3900 psig

  15. Licensing of spent fuel dry storage and consolidated rod storage

    International Nuclear Information System (INIS)

    Bailey, W.J.

    1990-02-01

    The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs

  16. Horizontal modular dry irradiated fuel storage system

    Science.gov (United States)

    Fischer, Larry E.; McInnes, Ian D.; Massey, John V.

    1988-01-01

    A horizontal, modular, dry, irradiated fuel storage system (10) includes a thin-walled canister (12) for containing irradiated fuel assemblies (20), which canister (12) can be positioned in a transfer cask (14) and transported in a horizontal manner from a fuel storage pool (18), to an intermediate-term storage facility. The storage system (10) includes a plurality of dry storage modules (26) which accept the canister (12) from the transfer cask (14) and provide for appropriate shielding about the canister (12). Each module (26) also provides for air cooling of the canister (12) to remove the decay heat of the irradiated fuel assemblies (20). The modules (26) can be interlocked so that each module (26) gains additional shielding from the next adjacent module (26). Hydraulic rams (30) are provided for inserting and removing the canisters (12) from the modules (26).

  17. Evolution of spent fuel dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Standring, Paul Nicholas [International Atomic Energy Agency, Vienna (Austria). Div. of Nuclear Fuel Cycle and Waste Technology; Takats, Ferenc [TS ENERCON KFT, Budapest (Hungary)

    2016-11-15

    Around 10,000 tHM of spent fuel is discharged per year from the nuclear power plants in operation. Whilst the bulk of spent fuel is still held in at reactor pools, 24 countries have developed storage facilities; either on the reactor site or away from the reactor site. Of the 146 operational AFR storage facilities about 80 % employ dry storage; the majority being deployed over the last 20 years. This reflects both the development of dry storage technology as well as changes in politics and trading relationships that have affected spent fuel management policies. The paper describes the various approaches to the back-end of the nuclear fuel cycle for power reactor fuels and provides data on deployed storage technologies.

  18. Underground storage tanks soft waste dislodging and conveyance

    International Nuclear Information System (INIS)

    Wellner, A.F.

    1993-10-01

    Currently 140 million liters (37 million gallons) of waste are stored in the single shell underground storage tanks (SSTs) at Hanford. The wastes contain both hazardous and radioactive constituents. This paper focuses on the Westinghouse Hanford Company's testing program for soft waste dislodging and conveyance technology. This program was initialized to investigate methods of dislodging and conveying soft waste. The main focus was on using air jets, water jets, and/or mechanical blades to dislodge the waste and air conveyance to convey the dislodged waste. These waste dislodging and conveyance technologies would be used in conjunction with a manipulator based retrieval system

  19. Closure report for underground storage tank 141-R3U1 and its associated underground piping

    Energy Technology Data Exchange (ETDEWEB)

    Mallon, B.J.; Blake, R.G.

    1994-03-01

    Underground storage tank UST 141-R3U1 at Lawrence Livermore National Laboratory (LLNL), was registered with the State Water Resources Control Board on June 27, 1984. This tank system consisted of a concrete tank, lined with polyvinyl chloride, and approximately 100 feet of PVC underground piping. UST 141-R3U1 had a capacity of 450 gallons. The underground piping connected three floor drains and one sink inside Building 141 to UST 141-R3U1. The wastewater collected in UST 141-R3U1 contained organic solvents, metals, and inorganic acids. On November 30, 1987, the 141-R3U1 tank system failed a precision tank test. The 141-R3U1 tank system was subsequently emptied and removed from service pending further precision tests to determine the location of the leak within the tank system. A precision tank test on February 5, 1988, was performed to confirm the November 30, 1987 test. Four additional precision tests were performed on this tank system between February 25, 1988, and March 6, 1988. The leak was located where the inlet piping from Building 141 penetrates the concrete side of UST 141-R3U1. The volume of wastewater that entered the backfill and soil around and/or beneath UST 141-R3U1 is unknown. On December 13, 1989, the LLNL Environmental Restoration Division submitted a plan to close UST 141-R3U1 and its associated piping to the Alameda County Department of Environmental Health. UST 141-R3U1 was closed as an UST, and shall be used instead as additional secondary containment for two aboveground storage tanks.

  20. Closure report for underground storage tank 141-R3U1 and its associated underground piping

    International Nuclear Information System (INIS)

    Mallon, B.J.; Blake, R.G.

    1994-03-01

    Underground storage tank UST 141-R3U1 at Lawrence Livermore National Laboratory (LLNL), was registered with the State Water Resources Control Board on June 27, 1984. This tank system consisted of a concrete tank, lined with polyvinyl chloride, and approximately 100 feet of PVC underground piping. UST 141-R3U1 had a capacity of 450 gallons. The underground piping connected three floor drains and one sink inside Building 141 to UST 141-R3U1. The wastewater collected in UST 141-R3U1 contained organic solvents, metals, and inorganic acids. On November 30, 1987, the 141-R3U1 tank system failed a precision tank test. The 141-R3U1 tank system was subsequently emptied and removed from service pending further precision tests to determine the location of the leak within the tank system. A precision tank test on February 5, 1988, was performed to confirm the November 30, 1987 test. Four additional precision tests were performed on this tank system between February 25, 1988, and March 6, 1988. The leak was located where the inlet piping from Building 141 penetrates the concrete side of UST 141-R3U1. The volume of wastewater that entered the backfill and soil around and/or beneath UST 141-R3U1 is unknown. On December 13, 1989, the LLNL Environmental Restoration Division submitted a plan to close UST 141-R3U1 and its associated piping to the Alameda County Department of Environmental Health. UST 141-R3U1 was closed as an UST, and shall be used instead as additional secondary containment for two aboveground storage tanks

  1. Underground storage development in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Sponheuer, T.

    1990-01-01

    As the demand for gas in the Federal Republic of Germany is increasingly dependent upon temperature, underground storage is becoming a more and more important tool for the adjustment of supply load factors to the patterns of gas demand. Total working gas capacity is expected to double by the year 2000. Capacity requirements must be planned for a design winter, but allowances must also be made for operational flexibility, but management of incidents and the decrease in deliverability mainly from porous rock storage fields towards the end of the withdrawal season. Storage development potential in the Federal Republic of Germany is adequate for these requirements. However, the substantial uncertainties associated with the various factors determining future storage needs, administrative and licensing procedures, difficulties with regard to storage site acceptance by the general public and the resulting long project lead times confront gas companies from the Federal Republic of Germany with a complex planning problem and a major technical and commercial challenge, considering the estimated capital outlay of 4 to 5 billion DM in 1988 Deutschmarks. To master this challenge and to be able to provide secure and competitive gas supplies, the gas industry must continue to operate in a market economy which remains undistorted by new legislation and regulation. (author). 11 figs

  2. Burnup credit in a dry storage module

    International Nuclear Information System (INIS)

    Thornton, J.R.

    1989-01-01

    Comparison of spent fuel storage expansion options available to Oconee Nuclear Station revealed that dry storage could be economically competitive with transshipment and rod consolidation. Economic competitiveness, however, mandated large unit capacity while existing cask handling facilities at Oconee severely limited size and weight. The dry storage concept determined to best satisfy these conflicting criteria is a 24 pressurized water reactor (PWR) fuel assembly capacity NUTECH Horizontal Modular Storage (NUHOMS) system. The Oconee version of the NUHOMS system takes advantage of burnup credit in demonstrating criticality safety. The burnup credit criticality analysis was performed by Duke Power Company's Design Engineering Department. This paper was prepared to summarize the criticality control design features employed in the Oconee NUHOMS-24P DSC basket and to describe the incentives for pursuing a burnup credit design. Principal criticality design parameters, criteria, and analysis methodology are also presented

  3. Underground storage tank soft waste dislodging and conveyance

    International Nuclear Information System (INIS)

    Wellner, A.F.S.

    1993-01-01

    The primary objective of this task is to demonstrate potential technical solutions and to acquire engineering data and information on the retrieval technologies applicable for use in retrieving waste from underground storage tanks. This task focuses on soft waste dislodging and conveyance technologies that would be used in conjunction with a manipulator-based retrieval system. This retrieval task focuses on Hanford single-shell tanks, but the results may also have applications to other waste retrieval problems. This work is part of the U.S. Department of Energy's (DOE's) Office of Technology Development, sponsored by the DOE's Richland Operations Office under the Underground Storage Tanks Integrated Demonstration (USTID) program. This task is one element of the whole waste dislodging and conveyance system in the USTID. The tank wastes contain both hazardous and radioactive constituents. This task focuses on the processes for dislodging and retrieving soft wastes, mainly sludge. Sludge consists primarily of heavy-metal, iron, and aluminum precipitates. Sludges vary greatly in their physical properties and may contain pockets of liquid. Sludges have been described as varying in consistency from thick slurry to sticky clay and as sandy with hard chunks of material. The waste is believed to have adhesive and cohesive properties. The quantitative physical properties of the wastes have yet to be measured. The waste simulants used in the testing program emulate the physical properties of the tank waste

  4. Dry storage cells for radioactive material

    International Nuclear Information System (INIS)

    Hartley, D.J.; Paget, F.T.W.

    1982-01-01

    A facility for posting irradiated nuclear fuel from a preparation cell of a dry storage complex into storage canisters located in buckets within a clean cell comprises a telescopic tubular port member for sealably connecting the preparation cell to a canister. In operation the closure of the canister is screened against contamination and withdrawn from the canister into the preparation cell via a retractable grab prior to posting of the fuel into the canister. (author)

  5. Dry Well Storage Facility conceptual design study

    International Nuclear Information System (INIS)

    1979-02-01

    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

  6. Dry Well Storage Facility conceptual design study

    Energy Technology Data Exchange (ETDEWEB)

    1979-02-01

    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.

  7. Improved Food Drying and Storage Training Manual.

    Science.gov (United States)

    Zweig, Peter R.; And Others

    This manual is intended to serve as a guide for those who are helping future Peace Corps volunteers to acquire basic food drying and storage skills. Included in the guide are lesson outlines and handouts for use in each of the 30 sessions of the course. Representative topics discussed in the individual sessions are scheduling, solar dryers,…

  8. Pickering dry storage - commissioning and initial operation

    International Nuclear Information System (INIS)

    Jonjev, S.

    1996-01-01

    Having commissioned all individual conventional and nuclear systems, the first Dry Storage Container (DSC) was loaded with four modules of 17 year cooled irradiated fuel (366 bundles) in the Auxiliary Irradiated Fuel Bay (AIFB) on November 29, 1995. After decontamination of the outer surface, and draining of water, the DSC was transported to the Used Fuel Dry Storage Facility (UFDSF) workshop, where it was vacuum dried, and then the lid was welded on. Following successful radiography test of the lid weld, the DSC was vacuum dried again and backfilled with Helium to a pressure of 930 mbar(a). The Helium leak test showed zero leakage (allowable leak rate is 1x10 -5 cc/sec). Finally, after loose contamination checks were performed and permanent safeguards seals were applied, the DSC was placed in the UFDSF storage area on January 23, 1996. Radiation fields at contact with the DSC surface were < 0.6 mrem/hr, and at the exterior surface of the storage building wall only 33 micro-rem/hr (far below the target of 250 micro-rem/hr). Therefore, the actual dose rates to general public (at the exclusion zone boundary) will be well below the design target of 1 % of the regulatory limit. (author). 3 refs., 2 tabs., 5 figs

  9. Pickering dry storage - commissioning and initial operation

    Energy Technology Data Exchange (ETDEWEB)

    Jonjev, S [Ontario Hydro, Pickering, ON (Canada). Pickering Generating Station

    1997-12-31

    Having commissioned all individual conventional and nuclear systems, the first Dry Storage Container (DSC) was loaded with four modules of 17 year cooled irradiated fuel (366 bundles) in the Auxiliary Irradiated Fuel Bay (AIFB) on November 29, 1995. After decontamination of the outer surface, and draining of water, the DSC was transported to the Used Fuel Dry Storage Facility (UFDSF) workshop, where it was vacuum dried, and then the lid was welded on. Following successful radiography test of the lid weld, the DSC was vacuum dried again and backfilled with Helium to a pressure of 930 mbar(a). The Helium leak test showed zero leakage (allowable leak rate is 1x10{sup -5} cc/sec). Finally, after loose contamination checks were performed and permanent safeguards seals were applied, the DSC was placed in the UFDSF storage area on January 23, 1996. Radiation fields at contact with the DSC surface were < 0.6 mrem/hr, and at the exterior surface of the storage building wall only 33 micro-rem/hr (far below the target of 250 micro-rem/hr). Therefore, the actual dose rates to general public (at the exclusion zone boundary) will be well below the design target of 1 % of the regulatory limit. (author). 3 refs., 2 tabs., 5 figs.

  10. Underground Storage Tank Integrated Demonstration (UST-ID)

    International Nuclear Information System (INIS)

    1994-02-01

    The DOE complex currently has 332 underground storage tanks (USTs) that have been used to process and store radioactive and chemical mixed waste generated from weapon materials production. Very little of the over 100 million gallons of high-level and low-level radioactive liquid waste has been treated and disposed of in final form. Two waste storage tank design types are prevalent across the DOE complex: single-shell wall and double-shell wall designs. They are made of stainless steel, concrete, and concrete with carbon steel liners, and their capacities vary from 5000 gallons (19 m 3 ) to 10 6 gallons (3785 m 3 ). The tanks have an overburden layer of soil ranging from a few feet to tens of feet. Responding to the need for remediation of tank waste, driven by Federal Facility Compliance Agreements (FFCAs) at all participating sites, the Underground Storage Tank Integrated Demonstration (UST-ID) Program was created by the US DOE Office of Technology Development in February 1991. Its mission is to focus the development, testing, and evaluation of remediation technologies within a system architecture to characterize, retrieve, treat to concentrate, and dispose of radioactive waste stored in USTs at DOE facilities. The ultimate goal is to provide safe and cost-effective solutions that are acceptable to the public and the regulators. The UST-ID has focused on five DOE locations: the Hanford Site, which is the host site, in Richland, Washington; the Fernald Site in Fernald, Ohio; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; the Oak Ridge Reservation in Oak Ridge, Tennessee, and the Savannah River Site in Savannah River, South Carolina

  11. Summary Report for Capsule Dry Storage Project

    Energy Technology Data Exchange (ETDEWEB)

    JOSEPHSON, W S

    2003-09-04

    There are 1.936 cesium (Cs) and strontium (Sr) capsules stored in pools at the Waste Encapsulation and Storage Facility (WESF). These capsules will be moved to dry storage on the Hanford Site as an interim measure to reduce risk. The Cs/Sr Capsule Dry Storage Project (CDSP) is conducted under the assumption the capsules will eventually be moved to the repository at Yucca Mountain, and the design criteria include requirements that will facilitate acceptance at the repository. The storage system must also permit retrieval of capsules in the event vitrification of the capsule contents is pursued. A cut away drawing of a typical cesium chloride (CsCI) capsule and the capsule property and geometry information are provided in Figure 1.1. Strontium fluoride (SrF{sub 2}) capsules are similar in design to CsCl capsules. Further details of capsule design, current state, and reference information are given later in this report and its references. Capsule production and life history is covered in WMP-16938, Capsule Characterization Report for Capsule Dry Storage Project, and is briefly summarized in Section 5.2 of this report.

  12. Underground storage tanks: State regulations and compliance strategies

    International Nuclear Information System (INIS)

    Robinson, J.E.

    1988-01-01

    In an effort to resolve underground storage tank (UST) management problems, several states and localities have moved ahead of EPA in the promulgation of UST regulations. Developed independently, these regulations represent different strategies for ensuring compliance: from an extensive set of permitting requirements that allow for the implementation of site-specific control measures to a uniform set of technical and operational requirements that vary according to installation date. For the tank owner, complying with these regulations can be a time-consuming and frustrating endeavor. However, during the course of several environmental audits of similar facilities in different states, useful strategies were observed or developed that enabled facilities to respond more effectively to requirements: these included computerization of files, designation of tank custodians, installation of low-maintenance equipment, and increased use of above-ground tanks. Of special additional interest was the wide variation in costs for similar tank services quoted by both private and government sources. These strategies are coupled with general observations on the efficacy of the various regulatory approaches to provide a field view that may be useful to tank owners and others involved in underground tank management and evaluation

  13. Robotic system for remote inspection of underground storage tanks

    International Nuclear Information System (INIS)

    Griebenow, B.L.; Martinson, L.M.

    1990-01-01

    Westinghouse Idaho Nuclear Company, Inc. (WINCO), operates the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy (DOE). WINCO's mission is to process government owned spent nuclear fuel. The process involves dissolving the fuel and extracting off uranium. The waste from this process is temporarily stored at the ICPP in underground storage tanks. The tanks were put in service between 1953 and 1966 and are operating 10 to 15 years beyond their design life. Five of the tanks will be replaced by 1998. The integrity of the remaining six tanks must be verified to continue their use until they can be replaced at a later data. In order to verify the tank integrity, a complete corrosion analysis must be performed. This analysis will require a remote visual inspection of the tank surfaces

  14. Advanced remediation, technology development in the underground storage tank

    International Nuclear Information System (INIS)

    Gates, T.E.; Gilchrist, R.L.

    1992-01-01

    Production of nuclear materials has been a major mission of the U. S. Department of Energy (DOE) over the last 50 years. These activities have contributed to a substantial accumulation of hazardous, radioactive, and mixed wastes. In 1989, the DOE established the Office of Environmental Restoration and Waste Management. This office coordinates and manages the DOE's remediation, waste minimization, and environmental compliance activities. It also has responsibility for waste generated by current operations. Within this office is the Office of Technology Development, which is responsible for providing technology improvements. This paper reports on integrated demonstrations which have been established to efficiently bring the best technologies to bear on the common needs of multiple DOE sites. One such need is resolution of the actions required for final closure and waste disposal of liquid (including sludge and salt cake) radioactive and chemical wastes that have been transferred to underground storage tanks

  15. Microbial Life in an Underground Gas Storage Reservoir

    Science.gov (United States)

    Bombach, Petra; van Almsick, Tobias; Richnow, Hans H.; Zenner, Matthias; Krüger, Martin

    2015-04-01

    While underground gas storage is technically well established for decades, the presence and activity of microorganisms in underground gas reservoirs have still hardly been explored today. Microbial life in underground gas reservoirs is controlled by moderate to high temperatures, elevated pressures, the availability of essential inorganic nutrients, and the availability of appropriate chemical energy sources. Microbial activity may affect the geochemical conditions and the gas composition in an underground reservoir by selective removal of anorganic and organic components from the stored gas and the formation water as well as by generation of metabolic products. From an economic point of view, microbial activities can lead to a loss of stored gas accompanied by a pressure decline in the reservoir, damage of technical equipment by biocorrosion, clogging processes through precipitates and biomass accumulation, and reservoir souring due to a deterioration of the gas quality. We present here results from molecular and cultivation-based methods to characterize microbial communities inhabiting a porous rock gas storage reservoir located in Southern Germany. Four reservoir water samples were obtained from three different geological horizons characterized by an ambient reservoir temperature of about 45 °C and an ambient reservoir pressure of about 92 bar at the time of sampling. A complementary water sample was taken at a water production well completed in a respective horizon but located outside the gas storage reservoir. Microbial community analysis by Illumina Sequencing of bacterial and archaeal 16S rRNA genes indicated the presence of phylogenetically diverse microbial communities of high compositional heterogeneity. In three out of four samples originating from the reservoir, the majority of bacterial sequences affiliated with members of the genera Eubacterium, Acetobacterium and Sporobacterium within Clostridiales, known for their fermenting capabilities. In

  16. Permanent Closure of MFC Biodiesel Underground Storage Tank 99ANL00013

    Energy Technology Data Exchange (ETDEWEB)

    Kerry L. Nisson

    2012-10-01

    This closure package documents the site assessment and permanent closure of the Materials and Fuels Complex biodiesel underground storage tank 99ANL00013 in accordance with the regulatory requirements established in 40 CFR 280.71, “Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.”

  17. Specialized video systems for use in underground storage tanks

    International Nuclear Information System (INIS)

    Heckendom, F.M.; Robinson, C.W.; Anderson, E.K.; Pardini, A.F.

    1994-01-01

    The Robotics Development Groups at the Savannah River Site and the Hanford site have developed remote video and photography systems for deployment in underground radioactive waste storage tanks at Department of Energy (DOE) sites as a part of the Office of Technology Development (OTD) program within DOE. Figure 1 shows the remote video/photography systems in a typical underground storage tank environment. Viewing and documenting the tank interiors and their associated annular spaces is an extremely valuable tool in characterizing their condition and contents and in controlling their remediation. Several specialized video/photography systems and robotic End Effectors have been fabricated that provide remote viewing and lighting. All are remotely deployable into and from the tank, and all viewing functions are remotely operated. Positioning all control components away from the facility prevents the potential for personnel exposure to radiation and contamination. Overview video systems, both monaural and stereo versions, include a camera, zoom lens, camera positioner, vertical deployment system, and positional feedback. Each independent video package can be inserted through a 100 mm (4 in.) diameter opening. A special attribute of these packages is their design to never get larger than the entry hole during operation and to be fully retrievable. The End Effector systems will be deployed on the large robotic Light Duty Utility Arm (LDUA) being developed by other portions of the OTD-DOE programs. The systems implement a multi-functional ''over the coax'' design that uses a single coaxial cable for all data and control signals over the more than 900 foot cable (or fiber optic) link

  18. A basic study on underground storage of LNG

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Min-Kyu; Lee, Kyung-Han; Kang, Sun-Duck [Korea Institute of Geology Mining and Materials, Taejon (KR)] (and others)

    1999-12-01

    In 1997, import of LNG was 11,378 thousand of about 2.3 billion US dollars. The demand of LNG(Liquefied Natural Gas) in Korea has been increased since 1987 with the rate of 20% annually. It is also estimated that this trend will be continued until 2010. Long-term estimation says that demand will increase with 9.1% and total demand of 2010 will be 23 million ton that is four times larger than that of 1994. Bases of unloading and store of LNG is necessary to complete the network of LNG distribution system to cover all of the country from import to final supply terminal at home. The construction plan of LNG bases with 49 tanks was published and is going on now at three bases, Pyungtaek, Incheon and Tongyoung. The total cost for this construction will be over 5,400 billion Won. All the LNG tanks are planned to build on the surface. The construction of LNG tanks on the surfaces is conventional but it damage the surface green area and is very vulnerable on safety, especially in Korea Peninsula with potentially unstable of military confrontation. And Korea is so small and limited in available land that it is not easy to find proper places for construction of more LNG tanks on surface. Underground LNG stores in rock will be a good alternative for tanks on surface in the view points of environmental and safety. It is also reported that it can be cheaper than that of on surfaces. It is well known that bed rocks in Korea is good to build underground structure like LNG stores. This report is basic research to seek for the possibility of LNG store construction in underground rocks. The important two questions on it is that whether it is possible technically and economically or not. The technical focus in this report is the stability of underground cavern for storage of LNG, energy conservation in operation, tightness against leakage of stored gas to surface and safety. Some statistic on LNG in Korea is given for this study with its future. (author). 25 refs., 36 tabs., 88 figs.

  19. Final version dry cask storage study

    International Nuclear Information System (INIS)

    1989-02-01

    This report was prepared in response to Section 5064 of the Nuclear Waste Policy Amendments Act of 1987 (the Amendments Act--Public Law 100-203), which directs the Secretary of Energy to conduct a study of the use of dry-cask-storage technology for storing spent fuel at the sites of civilian nuclear reactors until a geologic repository is available. In conducting this study, whose results are being reported to the Congress, the Secretary was to consider such factors as costs, effects on human health and the environment, and the extent to which the Nuclear Waste Fund can and should be used to provide funds for at-reactor storage. In addition, the Secretary was to consult with the Nuclear Regulatory Commission (NRC), include NRC comments in the report, and solicit the views of State and local governments and the public. The study performed in response to these requirements was based largely on data published by the DOE or the NRC or included in documents issued by the DOE. Among the DOE documents are the 1987 MRS proposal to the Congress and a subsequent report, prepared to supply the Congress with additional information on the MRS facility. Because in evaluating dry storage at reactor sites it is necessary to take into account other options for meeting storage needs, this study covered all forms of at-reactor storage. 107 refs., 15 figs., 10 tabs

  20. Lower Colorado River GRP Underground Storage Tank Sites (Closed), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  1. Lower Colorado River GRP Underground Storage Tank Sites (Open), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  2. Control system design for robotic underground storage tank inspection systems

    International Nuclear Information System (INIS)

    Kiebel, G.R.

    1994-09-01

    Control and data acquisition systems for robotic inspection and surveillance systems used in nuclear waste applications must be capable, versatile, and adaptable to changing conditions. The nuclear waste remediation application is dynamic -- requirements change as public policy is constantly re-examined and refocused, and as technology in this area advances. Control and data acquisition systems must adapt to these changing conditions and be able to accommodate future missions, both predictable and unexpected. This paper describes the control and data acquisition system for the Light Duty Utility Arm (LDUA) System that is being developed for remote surveillance and inspection of underground storage tanks at the Hanford Site and other US Department of Energy (DOE) sites. It is a high-performance system which has been designed for future growth. The priority mission at the Hanford site is to retrieve the waste generated by 50 years of production from its present storage and process it for final disposal. The LDUA will help to gather information about the waste and the tanks it is stored in to better plan and execute the cleanup mission

  3. Using virtual objects to aid underground storage tank teleoperation

    International Nuclear Information System (INIS)

    Anderson, R.J.; Davies, B.

    1994-01-01

    In this paper we describe an algorithm by which obstructions and surface features in an underground storage tank can be modeled and used to generate virtual barrier function for a real-time telerobotic system, which provides an aid to the operator for both real-time obstacle avoidance and for surface tracking. The algorithm requires that the slave's tool and every object in the waste storage tank be decomposed into convex polyhedral primitives, with the waste surface modeled by triangular prisms. Intrusion distance and extraction vectors are then derived at every time step by applying Gilbert's polyhedra distance algorithm, which has been adapted for the task. This information is then used to determine the compression and location of nonlinear virtual spring-dampers whose total force is summed and applied to the manipulator/teleoperator system. Experimental results using a PUMA 560 and a simulated waste surface validate the approach, showing that it is possible to compute the algorithm and generate smooth, realistic pseudo forces for the teleoperator system using standard VME bus hardware

  4. Underground storage. Study of radwaste storage in deep geological formations: environmental protection

    International Nuclear Information System (INIS)

    Hoorelbeke, J.M.

    1993-01-01

    The purpose of the Agence nationale pour la gestion des dechets radioactifs (Andra) is to monitor the management methods and storage of radioactive waste produced in France. The agency has this undertaken a vast study program for the evaluation of the management conditions of long-life radwaste, which cannot be stored indefinitely in shallow-ground repositories. Underground laboratories are investigating the feasibility of a possible solution which is to store radwaste in a deep geological layer. However, there will be no decision on this type of storage before the year 2006. 7 figs

  5. Criticality studies for dry storage cask

    International Nuclear Information System (INIS)

    Krishnani, P.D.; Srinivasan, K.R.

    1993-01-01

    Spent nuclear fuel from Tarapur Atomic Power Station (TAPS) is stored in a storage pool located inside the reactor building. The capacity of this pool was initially to meet storage requirements of 528 bundles which was later augmented from time to time. Since the enhanced capacity was also getting exhausted, setting up of a storage pool away from reactor was envisaged. As an interim measure, the dry storage casks were designed to store the spent fuel already cooled for a few years in the storage pools. If water enters the cask, the cask interior may be covered with steam water or air-water mixture. This paper gives the results of criticality calculations for storage cask under various conditions of steam water mixture, using the computer code LWRBOX. In these calculations, it has been assumed that the cask contains the most reactive fuel assemblies of reload-1 at zero burnup. It also gives the comparison of some of the results with General Electric (GE) calculations. (author). 3 refs., 1 fig., 2 tabs

  6. The cascad spent fuel dry storage facility

    International Nuclear Information System (INIS)

    Guay, P.; Bonnet, C.

    1991-01-01

    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

  7. Underground storage tank - Integrated Demonstration Technical Task Plan master schedule

    International Nuclear Information System (INIS)

    Johnson, C.M.

    1994-08-01

    This document provides an integrated programmatic schedule (i.e., Master Schedule) for the U.S. Department of Energy (DOE) Underground Storage Tank-Integrated Demonstration (UST-ID) Program. It includes top-level schedule and related information for the DOE Office of Technology Development (EM-50) UST-ID activities. The information is based upon the fiscal year (FY) 1994 technical task plans (TTPS) and has been prepared as a baseline information resource for program participants. The Master Schedule contains Level 0 and Level 1 program schedules for the UST-ID Program. This document is one of a number of programmatic documents developed to support and manage the UST-ID activities. It is composed of the following sections: Program Overview - provides a summary background of the UST-ID Program. This summary addresses the mission, scope, and organizational structure of the program; Activity Description - provides a programmatic description of UST-ID technology development activities and lists the key milestones for the UST-ID systems. Master Schedules - contains the Level 0 and Level 1 programmatic schedules for the UST-ID systems. References - lists the UST-ID programmatic documents used as a basis for preparing the Master Schedule. The appendixes contain additional details related to site-specific technology applications

  8. A risk-based approach to prioritize underground storage tanks

    International Nuclear Information System (INIS)

    Chidambariah, V.; Travis, C.C.; Trabalka, J.R.; Thomas, J.K.

    1992-01-01

    The purpose of this paper is to present a risk-based approach for rapid prioritization of low level liquid radioactive waste underground storage tanks (LLLW USTs) for possible interim corrective measures and/or ultimate closure. The ranking of LLLW USTs is needed to ensure that tanks with the greatest potential for adverse impact on the environment and human health receive top priority for further evaluation and remediation. Wastes from the LLLW USTs at the Oak Ridge National Laboratory (ORNL) were pumped out at the time the tanks were removed from service. The residual liquids and sludge contain a mixture of radionuclides and chemicals. Contaminants of concern that were identified in the liquid phase of the inactive LLLW USTs include, the radionuclides, 9O Sr, 137 Cs and 233 U and the chemicals, carbon tetrachloride, trichloroethene, tetrachloroethene, methyl ethyl ketone, mercury, lead and chromium. The risk-based approach for prioritization of the LLLW USTs is based upon three major criteria: (1) leaking characteristics of the tank; (2) location of the tanks; and (3) toxic potential of the tank contents

  9. Dry storage of irradiated nuclear fuel

    International Nuclear Information System (INIS)

    Tolmie, R.D.

    1983-01-01

    In transferring radioactive material between the preparation and clean chambers of a dry storage complex, irradiated nuclear fuel is posted from the preparation chamber to a sealable canister supported in a closable bucket in the clean chamber, or a contaminated sealed canister is posted from a closed bucket in the clean chamber into the preparation chamber by using a facility comprising two coaxial tubes constituting a closable orifice between the two chambers, the tubes providing sealing means for the bucket, and masking means for the bucket and canister closures together with means for withdrawing the closures into the preparation chamber. (author)

  10. Dry storage cell for radioactive material

    International Nuclear Information System (INIS)

    Bradley, N.

    1982-01-01

    In a dry storage cell for irradiated nuclear fuel or other highly active waste, cooling air flow is by natural draught in heat exchange with fuel containing canisters housed in channels. To inhibit corrosion by ensuring that the temperature of the air flowing over the canisters does not fall below the dew point when heat generation by decay has fallen, a fraction of the heat energy transferred to the cooling air is recirculated to the air upstream of the canisters. Recirculation of heat energy is effected by recirculation of a fraction of the hot air from downstream of the canisters. (author)

  11. New developments in dry spent fuel storage

    International Nuclear Information System (INIS)

    Bonnet, C.; Chevalier, Ph.

    2001-01-01

    As shown in various new examples, HABOG facility (Netherlands), CERNAVODA (Candu - Romania), KOZLODUY (WWER - Bulgaria), CHERNOBYL ( RMBK - Ukraine), MAYAK (Spent Fuel from submarine and Icebreakers - Russia), recent studies allow to confirm the flexibility and performances of the CASCAD system proposed by SGN, both in safety and operability, for the dry storage of main kinds of spent fuel. The main features are: A multiple containment barrier system: as required by international regulation, 2 independent barriers are provided (tight canister and storage pit); Passive cooling, while the Fuel Assemblies are stored in an inert atmosphere and under conditions of temperature preventing from degradation of rod cladding; Sub-criticality controlled by adequate arrangements in any conditions; Safe facility meeting ICPR 60 Requirements as well as all applicable regulations (including severe weather conditions and earthquake); Safe handling operations; Retrievability of the spent fuel either during storage period or at the end of planned storage period (100 years); Future Decommissioning of the facility facilitated through design optimisation; Construction and operating cost-effectiveness. (author)

  12. Plan of deep underground construction for investigations on high-level radioactive waste storage

    International Nuclear Information System (INIS)

    Mayanovskij, M.S.

    1996-01-01

    The program of studies of the Japanese PNC corporation on construction of deep underground storage for high-level radioactive wastes is presented. The program is intended for 20 years. The total construction costs equal about 20 billion yen. The total cost of the project is equal to 60 billion yen. The underground part is planned to reach 1000 m depth

  13. Characterization of underground storage tank sludge using fourier transform infrared photoacoustic spectroscopy

    International Nuclear Information System (INIS)

    Luo, S.; Bajic, S.J.; Jones, R.W.

    1994-01-01

    Analysis of underground storage tank (UST) contents is critical for the determination of proper disposal protocols and storage procedures of nuclear waste materials. Tank volume reduction processes during the 1940's and 50's have produced a waste form that compositionally varies widely and has a consistency that ranges from paste like sludge to saltcake. The heterogeneity and chemical reactivity of the waste form makes analysis difficult by most conventional methods which require extensive sample preparation. In this paper, a method is presented to characterize nuclear waste from UST's at the Westinghouse Hanford Site in Washington State, using Fourier transform infrared-photoacoustic spectroscopy (FTIR-PAS). FTIR-PAS measurements on milligram amounts of surrogate sludge samples have been used to accurately identify phosphate, sulfate, nitrite, nitrate and ferrocyanide components. A simple sample preparation method was followed to provide a reproducible homogeneous sample for quantitative analysis. The sample preparation method involved freeze drying the sludge sample prior to analysis to prevent the migration of soluble species. Conventional drying (e.g., air or, oven) leads to the formation of crystals near the surface where evaporation occurs. Sample preparation as well as the analytical utility of this method will be discussed

  14. Leaking Underground Storage Tank Points, Region 9 Indian Country, 2017, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains point features that represent Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. This dataset contains facility name and...

  15. Environmental Protection: Improved Inspections and Enforcement Would Ensure Safer Underground Storage Tanks

    National Research Council Canada - National Science Library

    Stephenson, John

    2001-01-01

    ...) Underground Storage Tank (UST) program. 1 The program is relevant to today's hearing because studies have shown that tanks that leak hazardous substances, such as methyl tertiary butyl ether (MTBE...

  16. Indian Country Leaking Underground Storage Tanks (LUST) Map Service, Region 9, 2016, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — This map service displays Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. The service is composed of three layers; one for each unique LUST...

  17. Indian Country Leaking Underground Storage Tank (LUST) Points, Region 9, 2016, US EPA Region 9

    Data.gov (United States)

    U.S. Environmental Protection Agency — This GIS dataset contains point features that represent Leaking Underground Storage Tanks in US EPA Region 9 Indian Country. This dataset contains facility name and...

  18. Integral Safety Assessment of Underground Storage of CO2 in Barendrecht, the Netherlands

    International Nuclear Information System (INIS)

    Vijgen, L.; Nitert, M.; Buijtendijk, B.; Van Dalen, A.

    2009-10-01

    The DCMR Environmental Protection Agency Rijnmond in the Netherlands conducted an Integral Safety Assessment of Underground Storage of CO2 in Barendrecht, the Netherlands, in cooperation with the involved safety and supervision authorities. The following aspects of the entire storage project and its safety issues have been examined: the compressor station in Pernis; the underground pipes between the compressor station and the injection locations; and the injection locations Barendrecht-Ziedewij and Barendrecht. [nl

  19. Preliminary proposed seismic design and evaluation criteria for new and existing underground hazardous materials storage tanks

    International Nuclear Information System (INIS)

    Kennedy, R.P.

    1991-01-01

    The document provides a recommended set of deterministic seismic design and evaluation criteria for either new or existing underground hazardous materials storage tanks placed in either the high hazard or moderate hazard usage catagories of UCRL-15910. The criteria given herein are consistent with and follow the same philosophy as those given in UCRL-15910 for the US Department of Energy facilities. This document is intended to supplement and amplify upon Reference 1 for underground hazardous materials storage tanks

  20. Estimating Residual Solids Volume In Underground Storage Tanks

    International Nuclear Information System (INIS)

    Clark, Jason L.; Worthy, S. Jason; Martin, Bruce A.; Tihey, John R.

    2014-01-01

    The Savannah River Site liquid waste system consists of multiple facilities to safely receive and store legacy radioactive waste, treat, and permanently dispose waste. The large underground storage tanks and associated equipment, known as the 'tank farms', include a complex interconnected transfer system which includes underground transfer pipelines and ancillary equipment to direct the flow of waste. The waste in the tanks is present in three forms: supernatant, sludge, and salt. The supernatant is a multi-component aqueous mixture, while sludge is a gel-like substance which consists of insoluble solids and entrapped supernatant. The waste from these tanks is retrieved and treated as sludge or salt. The high level (radioactive) fraction of the waste is vitrified into a glass waste form, while the low-level waste is immobilized in a cementitious grout waste form called saltstone. Once the waste is retrieved and processed, the tanks are closed via removing the bulk of the waste, chemical cleaning, heel removal, stabilizing remaining residuals with tailored grout formulations and severing/sealing external penetrations. The comprehensive liquid waste disposition system, currently managed by Savannah River Remediation, consists of 1) safe storage and retrieval of the waste as it is prepared for permanent disposition; (2) definition of the waste processing techniques utilized to separate the high-level waste fraction/low-level waste fraction; (3) disposition of LLW in saltstone; (4) disposition of the HLW in glass; and (5) closure state of the facilities, including tanks. This paper focuses on determining the effectiveness of waste removal campaigns through monitoring the volume of residual solids in the waste tanks. Volume estimates of the residual solids are performed by creating a map of the residual solids on the waste tank bottom using video and still digital images. The map is then used to calculate the volume of solids remaining in the waste tank. The ability to

  1. Structural analysis of underground gunite storage tanks. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This report documents the structural analysis of the 50-ft diameter underground gunite storage tanks constructed in 1943 and located in the Oak Ridge National Laboratory (ORNL) South Tank Farm, known as Facility 3507 in the 3500-3999 area. The six gunite tanks (W-5 through W-10) are spaced in a 2 {times} 3 matrix at 60 ft on centers with 6 ft of soil cover. Each tank (Figures 1, 2, and 3) has an inside diameter of 50 ft, a 12-ft vertical sidewall having a thickness of 6 in. (there is an additional 1.5-in. inner liner for much of the height), and a spherical domed roof (nominal thickness is 10 in.) rising another 6 ft, 3 in. at the center of the tank. The thickness of both the sidewall and the domed roof increases to 30 in. near their juncture. The tank floor is nominally 3-in. thick, except at the juncture with the wall where the thickness increases to 9 in. The tanks are constructed of gunite (a mixture of Portland cement, sand, and water in the form of a mortar) sprayed from the nozzle of a cement gun against a form or a solid surface. The floor and the dome are reinforced with one layer of welded wire mesh and reinforcing rods placed in the radial direction. The sidewall is reinforced with three layers of welded wire mesh, vertical {1/2}-in. rods, and 21 horizontal rebar hoops (attached to the vertical rods) post-tensioned to 35,000 psi stress. The haunch at the sidewall/roof junction is reinforced with 17 horizontal rebar hoops post-tensioned with 35,000 to 40,000 psi stress. The yield strength of the post-tensioning steel rods is specified to be 60,000 psi, and all other steel is 40,000 psi steel. The specified 28-day design strength of the gunite is 5,000 psi.

  2. Structural analysis of underground gunite storage tanks. Environmental Restoration Program

    International Nuclear Information System (INIS)

    1995-08-01

    This report documents the structural analysis of the 50-ft diameter underground gunite storage tanks constructed in 1943 and located in the Oak Ridge National Laboratory (ORNL) South Tank Farm, known as Facility 3507 in the 3500-3999 area. The six gunite tanks (W-5 through W-10) are spaced in a 2 x 3 matrix at 60 ft on centers with 6 ft of soil cover. Each tank (Figures 1, 2, and 3) has an inside diameter of 50 ft, a 12-ft vertical sidewall having a thickness of 6 in. (there is an additional 1.5-in. inner liner for much of the height), and a spherical domed roof (nominal thickness is 10 in.) rising another 6 ft, 3 in. at the center of the tank. The thickness of both the sidewall and the domed roof increases to 30 in. near their juncture. The tank floor is nominally 3-in. thick, except at the juncture with the wall where the thickness increases to 9 in. The tanks are constructed of gunite (a mixture of Portland cement, sand, and water in the form of a mortar) sprayed from the nozzle of a cement gun against a form or a solid surface. The floor and the dome are reinforced with one layer of welded wire mesh and reinforcing rods placed in the radial direction. The sidewall is reinforced with three layers of welded wire mesh, vertical 1/2-in. rods, and 21 horizontal rebar hoops (attached to the vertical rods) post-tensioned to 35,000 psi stress. The haunch at the sidewall/roof junction is reinforced with 17 horizontal rebar hoops post-tensioned with 35,000 to 40,000 psi stress. The yield strength of the post-tensioning steel rods is specified to be 60,000 psi, and all other steel is 40,000 psi steel. The specified 28-day design strength of the gunite is 5,000 psi

  3. Spent fuel dry storage in Hungary

    International Nuclear Information System (INIS)

    Buday, G.; Szabo, B.; Oerdoegh, M.; Takats, F.

    1999-01-01

    Paks Nuclear Power Plant is the only NPP in Hungary. It has four WWER-440 type reactor units. Since 1989, approximately 40-50% of the total annual electricity generation of the country has been supplied by this plant. The fresh fuel is imported from Russia. Most of the spent fuel assemblies have been shipped back to Russia. Difficulties with spent fuel transportation to Russia have begun in 1992. Since that time, some of the shipments were delayed, some of them were completely cancelled, thus creating a backlog of spent fuel filling all storage positions of the plant. To provide assurance of the continued operation, Paks NPPs management decided to implement an independent spent fuel storage facility and chose GEC-Althom's MVDS design. The construction of the facility started in February 1995 and the first spent fuel assembly was placed in the store in September 1997. The paper gives an overview of the situation, describing the conditions leading to the construction of the dry storage facility at Paks and its implementation. Finally, some information is given about the new Public Agency for Radioactive Waste Management established this year and responsible for managing the issues related to spent fuel management. (author)

  4. Emerging risk issues in underground storage of bituminous coal

    Energy Technology Data Exchange (ETDEWEB)

    Sipila, J.

    2013-11-01

    This thesis aims to address the root causes and means of prevention, mitigation and other improvements to the challenges from smouldering fires, coal freezing and occupational risk in an underground storage silo built into granite bedrock. In addition, appropriate performance indicators are suggested, and the benefits of the recommended or adopted actions are estimated. The issues and observed incidents demonstrate hazards that are largely classified to represent issues of emerging risk. To reduce the fire risk, successful measures included bottom maintenance door sealing and modified design of silo filling and discharge. The assessed benefits of these actions suggest a payback period of only about 10 days, assuming that, without these measures, a fire like the one in 2008 could occur once in four years. Additional recommendations are made to reduce air flow through the coal bed and near the silo ceiling, and to improve nitrogen purging at the hoppers. Filling with subzero coal can freeze silo drains, resulting in water inflow and further freezing to hamper discharge. As the heat flow is unlike any previously known cases of coal freezing, conventional mitigation e.g. by freeze conditioning agents, would not help. After implementing modified filling procedures for cold coal, no severe freezing cases have occurred. Safety advantages from the automated and remotely controlled operation do not necessarily apply under exceptional circumstances requiring human involvement. As preventive measures, protection has been sought from additional technical barriers and training effort. The rarity of serious incidents is a challenge in demonstrating success, but also emphasizes the importance of using leading (not only lagging) safety performance indicators for measurable safety promotion. In contrast, suitable leading performance indicators of the fire risk have been suggested for deliveries as an index of coal properties and for storage (gas emissions and temperature

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

    International Nuclear Information System (INIS)

    Endo, Yoshihiro.

    1997-01-01

    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.)

  6. A present status for dry storage of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bang, K. S.; Lee, J. C.; Park, H. Y.; Seo, K. S

    2003-04-01

    National policy for management of a spent nuclear fuel does not establish in Korea yet. A storage capacity of a storage pool that is to store the spent nuclear fuel will be exceeded an amount of accumulation from the first Woljin nuclear power plant in 2007. Therefore it is necessary that dry storage facility is secured to store safely the spent nuclear fuel on site of the nuclear power plant until national policy for a back-end spent nuclear fuel cycle is established. In order to store safely spent nuclear fuel, it is important that the present status and technology on dry storage of spent nuclear fuel is looked over. Therefore, the present status on dry storage of spent nuclear fuel was analyzed so as to develop dry storage system and choose a proper dry storage method domestic.

  7. Engineering and safety features of modular vault dry storage

    International Nuclear Information System (INIS)

    Deacon, D.; Wheeler, D.J.

    1984-01-01

    This paper discusses the need for interim dry storage and reviews detailed features of the Modular Vault Dry storage concept. The concept meets three basic utility requirements. Firstly, the technology and safety features have been demonstrated on existing plant; secondly, it can be built and licensed in an acceptably short timescale; and thirdly, economic analysis shows that a modular vault dry store is often the cheapest option for interim storage

  8. Nondestructive Examination Guidance for Dry Storage Casks

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Ryan M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Suffield, Sarah R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hirt, Evelyn H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Suter, Jonathan D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lareau, John P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zhuge, Jing Wei [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qiao, Hong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Moran, Traci L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ramuhalli, Pradeep [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-30

    In this report, an assessment of NDE methods is performed for components of NUHOMS 80 and 102 dry storage system components in an effort to assist NRC staff with review of license renewal applications. The report considers concrete components associated with the horizontal storage modules (HSMs) as well as metal components in the HSMs. In addition, the report considers the dry shielded canister (DSC). Scope is limited to NDE methods that are considered most likely to be proposed by licensees. The document, ACI 349.3R, Evaluation of Existing Nuclear Safety-Related Concrete Structures, is used as the basis for the majority of the NDE methods summarized for inspecting HSM concrete components. Two other documents, ACI 228.2R, Nondestructive Test Methods for Evaluation of Concrete in Structures, and ORNL/TM-2007/191, Inspection of Nuclear Power Plant Structure--Overview of Methods and Related Application, supplement the list with additional technologies that are considered applicable. For the canister, the ASME B&PV Code is used as the basis for NDE methods considered, along with currently funded efforts through industry (Electric Power Research Institute [EPRI]) and the U.S. Department of Energy (DOE) to develop inspection technologies for canisters. The report provides a description of HSM and DSC components with a focus on those aspects of design considered relevant to inspection. This is followed by a brief description of other concrete structural components such as bridge decks, dams, and reactor containment structures in an effort to facilitate comparison between these structures and HSM concrete components and infer which NDE methods may work best for certain HSM concrete components based on experience with these other structures. Brief overviews of the NDE methods are provided with a focus on issues and influencing factors that may impact implementation or performance. An analysis is performed to determine which NDE methods are most applicable to specific

  9. Comparison of wet and dry storage of spent nuclear fuels

    International Nuclear Information System (INIS)

    Soederman, E.

    1998-06-01

    Technologies for interim storage of spent nuclear fuels are reviewed. Pros and cons of wet and dry storage are discussed. No conclusions about preferences for one or the other technologies can be made

  10. Hydrogen storage materials and method of making by dry homogenation

    Science.gov (United States)

    Jensen, Craig M.; Zidan, Ragaiy A.

    2002-01-01

    Dry homogenized metal hydrides, in particular aluminum hydride compounds, as a material for reversible hydrogen storage is provided. The reversible hydrogen storage material comprises a dry homogenized material having transition metal catalytic sites on a metal aluminum hydride compound, or mixtures of metal aluminum hydride compounds. A method of making such reversible hydrogen storage materials by dry doping is also provided and comprises the steps of dry homogenizing metal hydrides by mechanical mixing, such as be crushing or ball milling a powder, of a metal aluminum hydride with a transition metal catalyst. In another aspect of the invention, a method of powering a vehicle apparatus with the reversible hydrogen storage material is provided.

  11. Dry storage of irradiated nuclear fuels and vitrified wastes

    International Nuclear Information System (INIS)

    Deacon, D.

    1982-01-01

    A review is given of the work of GEC Energy Systems Ltd. over the years in the dry storage of irradiated fuel. The dry-storage module (designated as Cell 4) for irradiated magnox fuel recently constructed at Wylfa nuclear power station is described. Development work on the long-term dry storage of irradiated oxide fuels is reported. Four different methods of storage are compared. These are the pond, vault, cask and caisson stores. It is concluded that there are important advantages with the passive air-cooled ESL dry stove. (U.K.)

  12. Corrosion assessment of dry fuel storage containers

    Energy Technology Data Exchange (ETDEWEB)

    Graves, C.E.

    1994-09-01

    The structural stability as a function of expected corrosion degradation of 75 dry fuel storage containers located in the 200 Area Low-Level Waste Burial Grounds was evaluated. These containers include 22 concrete burial containers, 13 55-gal (208-l) drums, and 40 Experimental Breeder Reactor II (EBR-II) transport/storage casks. All containers are buried beneath at least 48 in. of soil and a heavy plastic tarp with the exception of 35 of the EBR-II casks which are exposed to atmosphere. A literature review revealed that little general corrosion is expected and pitting corrosion of the carbon steel used as the exterior shell for all containers (with the exception of the concrete containers) will occur at a maximum rate of 3.5 mil/yr. Penetration from pitting of the exterior shell of the 208-l drums and EBR-II casks is calculated to occur after 18 and 71 years of burial, respectively. The internal construction beneath the shell would be expected to preclude containment breach, however, for the drums and casks. The estimates for structural failure of the external shells, large-scale shell deterioration due to corrosion, are considerably longer, 39 and 150 years respectively for the drums and casks. The concrete burial containers are expected to withstand a service life of 50 years.

  13. Structural analysis of ORNL underground gunite waste storage tanks

    International Nuclear Information System (INIS)

    Fricke, K.E.

    1995-01-01

    The North Tank Farm (NTF) and the South Tank Farm (STF) located at ORNL contains 8 underground waste storage tanks which were built around 1943. The tanks were used to collect and store the liquid portion of the radioactive and/or hazardous chemical wastes produced as part of normal facility operations at ORNL, but are no longer part of the active Low Level Liquid Waste system of the Laboratory. The tanks were constructed of gunite. The six STF tanks are 50 ft in diameter, and have a 12 ft sidewall, and an arched dome rising another 6.25 ft. The sidewall are 6 in. thick and have an additional 1.5 in. gunite liner on the inside. There is a thickened ring at the wall-dome juncture. The dome consists of two 5 in. layers of gunite. The two tanks in the NTF are similar, but smaller, having a 25 ft diameter, no inner liner, and a dome thickness of 3.5 in. Both sets of tanks have welded wire mesh and vertical rebars in the walls, welded wire mesh in the domes, and horizontal reinforcing hoop bars pre-tensioned to 35 to 40 ksi stress in the walls and thickened ring. The eight tanks are entirely buried under a 6 ft layer of soil cover. The present condition of the tanks is not accurately known, since access to them is extremely limited. In order to evaluate the structural capability of the tanks, a finite element analysis of each size tank was performed. Both static and seismic loads were considered. Three sludge levels, empty, half-full, and full were evaluated. In the STF analysis, the effects of wall deterioration and group spacing were evaluated. These analyses found that the weakest element in the tanks is the steel resisting the circumferential (or hoop) forces in the dome ring, a fact verified separately by an independent reviewer. However, the hoop steel has an adequate demand/capacity ratio. Buckling of the dome and the tank walls is not a concern

  14. UNDERGROUND

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1993-11-15

    Full text: Cossetted deep underground, sheltered from cosmic ray noise, has always been a favourite haunt of neutrino physicists. Already in the 1930s, significant limits were obtained by taking a geiger counter down in Holborn 'tube' station, one of the deepest in London's underground system. Since then, neutrino physicists have popped up in many unlikely places - gold mines, salt mines, and road tunnels deep under mountain chains. Two such locations - the 1MB (Irvine/ Michigan/Brookhaven) detector 600 metres below ground in an Ohio salt mine, and the Kamiokande apparatus 1000m underground 300 km west of Tokyo - picked up neutrinos on 23 February 1987 from the famous 1987A supernova. Purpose-built underground laboratories have made life easier, notably the Italian Gran Sasso Laboratory near Rome, 1.4 kilometres below the surface, and the Russian Baksan Neutrino Observatory under Mount Andyrchi in the Caucasus range. Gran Sasso houses ICARUS (April, page 15), Gallex, Borexino, Macro and the LVD Large Volume Detector, while Baksan is the home of the SAGE gallium-based solar neutrino experiment. Elsewhere, important ongoing underground neutrino experiments include Soudan II in the US (April, page 16), the Canadian Sudbury Neutrino Observatory with its heavy water target (January 1990, page 23), and Superkamiokande in Japan (May 1991, page 8)

  15. UNDERGROUND

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    Full text: Cossetted deep underground, sheltered from cosmic ray noise, has always been a favourite haunt of neutrino physicists. Already in the 1930s, significant limits were obtained by taking a geiger counter down in Holborn 'tube' station, one of the deepest in London's underground system. Since then, neutrino physicists have popped up in many unlikely places - gold mines, salt mines, and road tunnels deep under mountain chains. Two such locations - the 1MB (Irvine/ Michigan/Brookhaven) detector 600 metres below ground in an Ohio salt mine, and the Kamiokande apparatus 1000m underground 300 km west of Tokyo - picked up neutrinos on 23 February 1987 from the famous 1987A supernova. Purpose-built underground laboratories have made life easier, notably the Italian Gran Sasso Laboratory near Rome, 1.4 kilometres below the surface, and the Russian Baksan Neutrino Observatory under Mount Andyrchi in the Caucasus range. Gran Sasso houses ICARUS (April, page 15), Gallex, Borexino, Macro and the LVD Large Volume Detector, while Baksan is the home of the SAGE gallium-based solar neutrino experiment. Elsewhere, important ongoing underground neutrino experiments include Soudan II in the US (April, page 16), the Canadian Sudbury Neutrino Observatory with its heavy water target (January 1990, page 23), and Superkamiokande in Japan (May 1991, page 8)

  16. Thermal Analysis of a Dry Storage Concept for Capsule Dry Storage Project

    International Nuclear Information System (INIS)

    JOSEPHSON, W.S.

    2003-01-01

    There are 1,936 cesium (Cs) and strontium (Sr) capsules stored in pools at the Waste Encapsulation and Storage Facility (WESF). These capsules will be moved to dry storage on the Hanford Site as an interim measure to reduce risk. The Cs/Sr Capsule Dry Storage Project is conducted under the assumption that the capsules will eventually be moved to the repository at Yucca Mountain, and the design criteria include requirements that will facilitate acceptance at the repository. The storage system must also permit retrieval of capsules in the event that vitrification of the capsule contents is pursued. The Capsule Advisory Panel (CAP) was created by the Project Manager for the Hanford Site Capsule Dry Storage Project (CDSP). The purpose of the CAP is to provide specific technical input to the CDSP; to identify design requirements; to ensure design requirements for the project are conservative and defensible; to identify and resolve emerging, critical technical issues, as requested; and to support technical reviews performed by regulatory organizations, as requested. The CAP will develop supporting and summary documents that can be used as part of the technical and safety bases for the CDSP. The purpose of capsule dry storage thermal analysis is to: (1) Summarize the pertinent thermal design requirements sent to vendors, (2) Summarize and address the assumptions that underlie those design requirements, (3) Demonstrate that an acceptable design exists that satisfies the requirements, (4) Identify key design features and phenomena that promote or impede design success, (5) Support other CAP analyses such as corrosion and integrity evaluations, and (6) Support the assessment of proposed designs. It is not the purpose of this report to optimize or fully analyze variations of postulated acceptable designs. The present evaluation will indicate the impact of various possible design features, but not systematically pursue design improvements obtainable through analysis

  17. Adaptation of magnesian cements to underground storage of nuclear wastes

    International Nuclear Information System (INIS)

    Dufournet, F.

    1987-01-01

    The aim of this thesis is the experimental study of magnesium oxychloride cements as filling materials for underground granitic cavities containing high level radioactive wastes. After a bibliographic study, mechanical properties are examined before and after setting, in function of the ratio MgO/MgCl 2 . Then behavior with water is investigated: swelling, cracking and leaching [fr

  18. Fructan dynamics in the underground organs of Chresta exsucca (Asteraceae, a dry season flowering species

    Directory of Open Access Journals (Sweden)

    Camila Silva dos Santos

    2017-11-01

    Full Text Available ABSTRACT Climatic seasonality has an influence on the phenology of native Cerrado plants. Herbs and subshrubs tend to flower in the rainy season, although some species of these habits flower in the dry season. Reserve carbohydrates, stored in the underground organs, are used to support phases of high energy-demand, but also may protect plants from damage during periods of environmental limitation. In this study we evaluated variation in fructan levels in the underground organs of field-grown plants of Chresta exsucca among different phenological phases. Chresta exsucca flowers in the dry season and possesses a diffuse underground system, which stores inulin-type fructans. Resprouting was continual during the sampling period. Oligosaccharide content was always higher than polysaccharide content, except during senescence, the only phase with an oligosaccharide: polysaccharide ratio < 1. Fructan accumulation occurred during vegetative growth until flowering. Fructan mobilization was prominent during resprouting until the beginning of vegetative growth. Fructans stored in the underground organs of C. exsucca serve to fulfill the energetic demands of development and maintenance of this complex structure. In this way, fructans are essential to the persistence of this species in the environment of the Cerrado by ensuring reproduction in harsh conditions, such as drought.

  19. Behavior of spent nuclear fuel and storage system components in dry interim storage.

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, A.B. Jr.; Gilbert, E.R.; Guenther, R.J.

    1982-08-01

    Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are stored in vaults and dry wells. Certain types of fuel are being stored in licensed dry storage facilities: Magnox fuel in vaults in the United Kingdom and organic-cooled reactor (OCR) fuel in silos in Canada. Dry storage demonstrations are under way for Zircaloy-clad fuel from boiling water reactors BWR's, pressurized heavy-water reactors (PHWRs), and pressurized water reactors (PWRs) in all four types of dry storage facilities. The demonstrations and related hot cell and laboratory tests are directed toward expanding the data base and establishing a licensing basis for dry storage of water reactor fuel. This report reviews the scope of dry interim storage technology, the performance of fuel and facility materials, the status of programs in several countries to license dry storage of water reactor fuel, and the characteristics of water reactor fuel that relate to dry storage conditions.

  20. Behavior of spent nuclear fuel and storage-system components in dry interim storage

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Gilbert, E.R.; Guenther, R.J.

    1982-08-01

    Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are stored in vaults and dry wells. Certain types of fuel are being stored in licensed dry storage facilities: Magnox fuel in vaults in the United Kingdom and organic-cooled reactor (OCR) fuel in silos in Canada. Dry storage demonstrations are under way for Zircaloy-clad fuel from boiling water reactors BWR's, pressurized heavy-water reactors (PHWRs), and pressurized water reactors (PWRs) in all four types of dry storage facilities. The demonstrations and related hot cell and laboratory tests are directed toward expanding the data base and establishing a licensing basis for dry storage of water reactor fuel. This report reviews the scope of dry interim storage technology, the performance of fuel and facility materials, the status of programs in several countries to license dry storage of water reactor fuel, and the characteristics of water reactor fuel that relate to dry storage conditions

  1. Materials in the environment of the fuel in dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Issard, H [TN International (Cogema Logistics) (France)

    2012-07-01

    Spent nuclear fuel has been stored safely in pools or dry systems in over 30 countries. The majority of IAEA Member States have not yet decided upon the ultimate disposition of their spent nuclear fuel: reprocessing or direct disposal. Interim storage is the current solution for these countries. For developing the technological knowledge data base, a continuation of the IAEA's spent fuel storage performance assessment was achieved. The objectives are: Investigate the dry storage systems and gather basic fuel behaviour assessment; Gather data on dry storage environment and cask materials; Evaluate long term behaviour of cask materials.

  2. Pursing other deep pockets: California's underground storage tank cleanup fund and insurance policies

    International Nuclear Information System (INIS)

    Almanza, P.R.

    1995-01-01

    When faced with a potentially very expensive environmental cleanup, most companies and individuals try to do the only sensible thing, which is to find out if anyone else will pay the bill. This presentation will outline two avenues that may provide a substantial financial contribution to environmental cleanups: (a) California's Underground Storage Tank Cleanup Fund and (b) insurance policies. The Underground Storage Tank Cleanup Fund was established in 1989 to help eligible owners and operators of petroleum underground storage tanks (USTs) to: (a) get reimbursed for costs of unauthorized releases of petroleum from USTs; (b) get reimbursed for damages awarded to third parties as a result of unauthorized releases of petroleum from USTs; and (c) meet federal and state requirements that the UST owner and/or operator be able to pay for cleanup costs and damages to third parties caused by unauthorized releases of petroleum

  3. Geological Feasibility of Underground Oil Storage in Jintan Salt Mine of China

    Directory of Open Access Journals (Sweden)

    Xilin Shi

    2017-01-01

    Full Text Available A number of large underground oil storage spaces will be constructed in deep salt mines in China in the coming years. According to the general geological survey, the first salt cavern oil storage base of China is planned to be built in Jintan salt mine. In this research, the geological feasibility of the salt mine for oil storage is identified in detail as follows. (1 The characteristics of regional structure, strata sediment, and impermeable layer distribution of Jintan salt mine were evaluated and analyzed. (2 The tightness of cap rock was evaluated in reviews of macroscopic geology and microscopic measuring. (3 According to the geological characteristics of Jintan salt mine, the specific targeted formation for building underground oil storage was chosen, and the sealing of nonsalt interlayers was evaluated. (4 Based on the sonar measuring results of the salt caverns, the characteristics of solution mining salt caverns were analyzed. In addition, the preferred way of underground oil storage construction was determined. (5 Finally, the results of closed well observation in solution mining salt caverns were assessed. The research results indicated that Jintan salt mine has the basic geological conditions for building large-scale underground oil storage.

  4. The underground retrievable storage (URS) high-level waste management concept

    International Nuclear Information System (INIS)

    Ramspott, L.D.

    1991-01-01

    This papers presents the concept of long-term underground retrievable storage (URS) of spent reactor fuel in unsaturated rock. Emplacement would be incremental and the system is planned to be experimental and flexible. The rationale for retrievability is examined, and a technical basis for 300-year retrievability is presented. Maximum isolation is the rationale for underground as opposed to surface storage. Although the potential repository site at Yucca Mountain Nevada would be suitable for a URS, alternate sites are discussed. The technical issues involved in licensing a URS for 300 years are simpler than licensing a 10,000 year repository. 16 refs

  5. Safety Aspects of Long Term Spent Fuel Dry Storage

    International Nuclear Information System (INIS)

    Botsch, Wolfgang; Smalian, S.; Hinterding, P.; Drotleff, H.; Voelzke, H.; Wolff, D.; Kasparek, E.

    2014-01-01

    As a consequence of the lack of a final repository for spent nuclear fuel (SF) and high level waste (HLW), long term interim storage of SF and HLW will be necessary. As with the storage of all radioactive materials, the long term storage of SF and HLW must conform to safety requirements. Safety aspects such as safe enclosure of radioactive materials, safe removal of decay heat, sub-criticality and avoidance of unnecessary radiation exposure must be achieved throughout the complete storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. After the events of Fukushima, the advantages of passively and inherently safe dry storage systems have become more obvious. In Germany, dry storage of SF in casks fulfils both transport and storage requirements. Mostly, storage facilities are designed as concrete buildings above the ground; one storage facility has also been built as a rock tunnel. In all these facilities the safe enclosure of radioactive materials in dry storage casks is achieved by a double-lid sealing system with surveillance of the sealing system. The safe removal of decay heat is ensured by the design of the storage containers and the storage facility, which also secures to reduce the radiation exposure to acceptable levels. TUV and BAM, who work as independent experts for the competent authorities, inform about spent fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields. All relevant safety issues such as safe enclosure, shielding, removal of decay heat and sub-criticality are checked and validated with state-of-the-art methods and computer codes before the license approval. In our presentation we discuss which of these aspects need to be examined closer for a long term interim storage. It is shown

  6. Modular dry storage of spent fuel

    International Nuclear Information System (INIS)

    Baxter, J.W.

    1982-01-01

    Long term uncertainties in US spent fuel reprocessing and storage policies and programs are forcing the electric utilities to consider means of storing spent fuel at the reactor site in increasing quantitities and for protracted periods. Utilities have taken initial steps in increasing storage capacity. Existing wet storage pools have in many cases been reracked to optimize their capacity for storing spent fuel assemblies

  7. Advantages on dry interim storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, L.S. [Centro Tecnologico da Marinha em Sao Paulo, Av. Professor Lineu Prestes 2468, 05508-900 Sao Paulo (Brazil); Rzyski, B.M. [IPEN/ CNEN-SP, 05508-000 Sao Paulo (Brazil)]. e-mail: romanato@ctmsp.mar.mil.br

    2006-07-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

  8. Advantages on dry interim storage for spent nuclear fuel

    International Nuclear Information System (INIS)

    Romanato, L.S.; Rzyski, B.M.

    2006-01-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

  9. Equipment designs for the spent LWR fuel dry storage demonstration

    International Nuclear Information System (INIS)

    Steffen, R.J.; Kurasch, D.H.; Hardin, R.T.; Schmitten, P.F.

    1980-01-01

    In conjunction with the Spent Fuel Handling and Packaging Program (SFHPP) equipment has been designed, fabricated and successfully utilized to demonstrate the packaging and interim dry storage of spent LWR fuel. Surface and near surface storage configurations containing PWR fuel assemblies are currently on test and generating baseline data. Specific areas of hardware design focused upon include storage cell components and the support related equipment associated with encapsulation, leak testing, lag storage, and emplacement operations

  10. Spent fuel behaviour during dry storage - a review

    International Nuclear Information System (INIS)

    Shivakumar, V.; Anantharaman, K.

    1997-09-01

    One of the strategies employed for management of spent fuel prior to their final disposal/reprocessing is their dry storage in casks, after they have been sufficiently cooled in spent fuel pools. In this interim storage, one of the main consideration is that the fuel should retain its integrity to ensure (a) radiological health hazard remains minimal and (b) the fuel is retrievable for down steam fuel management processes such as geological disposal or reprocessing. For dry storage of spent fuel in air, oxidation of the exposed UO 2 is the most severe of phenomena affecting the integrity of fuel. This is kept within acceptable limits for desired storage time by limiting the fuel temperature in the storage cask. The limit on the fuel temperature is met by having suitable limits on maximum burn-up of fuel, minimum cooling period in storage pool and optimum arrangement of fuel bundles in the storage cask from heat removal considerations. The oxidation of UO 2 by moist air has more deleterious effects on the integrity of fuel than that by dry air. The removal of moisture from the storage cask is therefore a very important aspect in dry storage practice. The kinetics of the oxidation phenomena at temperatures expected during dry storage in air is very slow and therefore the majority of the existing data is based on extrapolation of data obtained at higher fuel temperatures. This and the complex effects of factors like fission products in fuel, radiolysis of storage medium etc. has necessitated in having a conservative limiting criteria. The data generated by various experimental programmes and results from the on going programmes have shown that dry storage is a safe and economical practice. (author)

  11. Dry storage of MTR spent fuel from the Argentine radioisotope production reactor RA-3

    International Nuclear Information System (INIS)

    Di Marco, A.; Gillaume, E.J.; Ruggirello, G.; Zaweruchi, A.

    1996-01-01

    The nuclear fuel elements of the RA-3 reactor consist in 19 rectangular fuel plates held in position by two lateral structural plates. The whole assembly is coupled to the lower nozzles that fits in the reactor core grid. The inner plates are 1.5 mm thick, 70.5 mm wide and 655 mm long and the outer plates are 100 mm longer. The fuel plates are formed by a core of an AI-U alloy co-laminated between two plates of Al. Enrichment is 90% 235 U. After being extracted from the reactor, the fuel elements have been let to cool down in the reactor storage pool and finally moved to the storage facility. This facility is a grid of vertical underground channels connected by a piping system. The system is filled with processed and controlled water. At the present the storage capacity of the facility is near to be depleted and some indications of deterioration of the fuel elements has been detected. Due to the present status of the facility and the spent fuel stored there, a decision has been taken to proceed to modify the present underwater storage to dry storage. The project consist in: a) Decontamination and conditioning of the storage channels to prepare them for dry storage. b) Disassembly of the fuel elements in hot cells in order to can only the active fuel plates in an adequate tight canister. c) The remnant structural pieces will be treated as low level waste. (author). 10 figs

  12. Optimization of basic parameters of cyclic operation of underground gas storages

    Directory of Open Access Journals (Sweden)

    Віктор Олександрович Заєць

    2015-04-01

    Full Text Available The problem of optimization of process parameters of cyclic operation of underground gas storages in gas mode is determined in the article. The target function is defined, expressing necessary capacity of compressor station for gas injection in the storage. Its minimization will find the necessary technological parameters, such as flow and reservoir pressure change over time. Limitations and target function are reduced to a linear form. Solution of problems is made by the simplex method

  13. Correction: Large-scale electricity storage utilizing reversible solid oxide cells combined with underground storage of CO2 and CH4

    DEFF Research Database (Denmark)

    Jensen, Søren Højgaard; Graves, Christopher R.; Mogensen, Mogens Bjerg

    2017-01-01

    Correction for ‘Large-scale electricity storage utilizing reversible solid oxide cells combined with underground storage of CO2 and CH4’ by S. H. Jensen et al., Energy Environ. Sci., 2015, 8, 2471–2479.......Correction for ‘Large-scale electricity storage utilizing reversible solid oxide cells combined with underground storage of CO2 and CH4’ by S. H. Jensen et al., Energy Environ. Sci., 2015, 8, 2471–2479....

  14. RCRA corrective action for underground storage tanks -- Subtitle C for Subtitle I

    International Nuclear Information System (INIS)

    1995-08-01

    The purpose of this report is to provide guidance to DOE and DOE contractor personnel responsible for planning and implementation of corrective measures addressing cleanup of releases of hazardous materials or regulated substances from underground storage tanks regulated under RCRA Subtitle C or Subtitle I

  15. The underground storage tank is the key; Der Speicher ist der Schluessel

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Jens-Peter

    2013-08-06

    Plus energy houses also succeed withoutpassive house insulation. Because the combination of solar collectors, ventilation and heat pump achieves excellent energy efficiency, if one preserves the solar heat in an underground storage tank. [German] Plusenergiehaeuser gelingen auch ohne Passivhausdaemmung. Denn die Kombination von Sonnenkollektoren, Lueftung und Waermepumpe erreicht eine ausgezeichnete energetische Effizienz, sofern man die Solarwaerme in einem Erdspeicher konserviert.

  16. Extensive optimisation analyses of the piping of two large underground gas storage ariel compressors

    NARCIS (Netherlands)

    Eijk, A.; Korst, H.J.C.; Ploumen, G.; Heyer, D.

    2007-01-01

    Two large identical 6-cylinder Ariel JGB/6 compressors of each 7.5 Mw, are used for the underground gas storage (UGS) plant of Essent in Epe, Germany. The compressors can be operated at a wide range of operating conditions, e.g. variable suction and discharge pressures, 2-stage mode during gas

  17. Advancing the US Department of Energy's Technologies through the Underground Storage Tank: Integrated Demonstration Program

    International Nuclear Information System (INIS)

    Gates, T.E.

    1993-01-01

    The principal objective of the Underground Storage Tank -- Integrated Demonstration Program is the demonstration and continued development of technologies suitable for the remediation of waste stored in underground storage tanks. The Underground Storage Tank Integrated Demonstration Program is the most complex of the integrated demonstration programs established under the management of the Office of Technology Development. The Program has the following five participating sites: Oak Ridge, Idaho, Fernald, Savannah River, and Hanford. Activities included within the Underground Storage Tank -- Integrated Demonstration are (1) characterizating radioactive and hazardous waste constituents, (2) determining the need and methodology for improving the stability of the waste form, (3) determining the performance requirements, (4) demonstrating barrier performance by instrumented field tests, natural analog studies, and modeling, (5) determining the need and method for destroying and stabilizing hazardous waste constituents, (6) developing and evaluating methods for retrieving, processing (pretreatment and treatment), and storing the waste on an interim basis, and (7) defining and evaluating waste packages, transportation options, and ultimate closure techniques including site restoration. The eventual objective is the transfer of new technologies as a system to full-scale remediation at the US Department of Energy complexes and sites in the private sector

  18. Instability risk analysis and risk assessment system establishment of underground storage caverns in bedded salt rock

    Science.gov (United States)

    Jing, Wenjun; Zhao, Yan

    2018-02-01

    Stability is an important part of geotechnical engineering research. The operating experiences of underground storage caverns in salt rock all around the world show that the stability of the caverns is the key problem of safe operation. Currently, the combination of theoretical analysis and numerical simulation are the mainly adopts method of reserve stability analysis. This paper introduces the concept of risk into the stability analysis of underground geotechnical structure, and studies the instability of underground storage cavern in salt rock from the perspective of risk analysis. Firstly, the definition and classification of cavern instability risk is proposed, and the damage mechanism is analyzed from the mechanical angle. Then the main stability evaluating indicators of cavern instability risk are proposed, and an evaluation method of cavern instability risk is put forward. Finally, the established cavern instability risk assessment system is applied to the analysis and prediction of cavern instability risk after 30 years of operation in a proposed storage cavern group in the Huai’an salt mine. This research can provide a useful theoretical base for the safe operation and management of underground storage caverns in salt rock.

  19. Bedrock instability of underground storage systems in the Czech Republic, Central Europe

    Czech Academy of Sciences Publication Activity Database

    Nováková, Lucie; Brož, Milan; Záruba, J.; Sosna, K.; Najser, J.; Rukavičková, L.; Franěk, J.; Rudajev, V.

    2016-01-01

    Roč. 13, č. 2 (2016), s. 315-325 ISSN 1672-7975 R&D Projects: GA MPO(CZ) FR-TI1/367 Institutional support: RVO:67985891 ; RVO:67985530 Keywords : underground storage * instability * seismicity * Bohemian Massif Subject RIV: DD - Geochemistry Impact factor: 0.796, year: 2016

  20. Paradigms of underground gas storage operation; Paradigmas del funcionamiento de un almacenamiento subterraneo de gas

    Energy Technology Data Exchange (ETDEWEB)

    Bonoris, Patricia; Vizcarra, Rodolfo; Buciak, Jorge [Companias Asociadas Petroleras S.A. (Argentina)

    2004-07-01

    The main objective of the study was to determine, for the underground storage of gas, the Current Useful Volume and Maximum Useful Current of operation, as well as have an acceptable interpretation that allows calculating the investment needed to reach this Maximum Usable Volume.

  1. VOLUMETRIC LEAK DETECTION IN LARGE UNDERGROUND STORAGE TANKS - VOLUME II: APPENDICES A-E

    Science.gov (United States)

    The program of experiments conducted at Griffiss Air Force Base was devised to expand the understanding of large underground storage tank behavior as it impacts the performance of volumetric leak detection testing. The report addresses three important questions about testing the ...

  2. 30 CFR 75.1912 - Fire suppression systems for permanent underground diesel fuel storage facilities.

    Science.gov (United States)

    2010-07-01

    ... Diesel-Powered Equipment § 75.1912 Fire suppression systems for permanent underground diesel fuel storage... system by a nationally recognized independent testing laboratory and appropriate for installation at a... recommended inspection and maintenance program and as required by the nationally recognized independent...

  3. Accelerated storage testing of freeze-dried Pseudomonas ...

    African Journals Online (AJOL)

    Accelerated storage testing of freeze-dried Pseudomonas fluorescens BTP1, ... of all P. fluorescens strains were not significantly different and thermal inactivation ... useful to the development of improved reference materials and samples held ...

  4. Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    D. H. Cox

    2001-06-01

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots

  5. Treatment of radioactive wastes from DOE underground storage tanks

    International Nuclear Information System (INIS)

    Collins, J.L.; Egan, B.Z.; Spencer, B.B.; Chase, C.W.; Anderson, K.K.; Bell, J.T.

    1994-01-01

    Bench-scale batch tests have been conducted with sludge and supernate tank waste from the Melton Valley Storage Tank (MVST) Facility at Oak Ridge National Laboratory (ORNL) to evaluate separation technology process for use in a comprehensive sludge processing flow sheet as a means of concentrating the radionuclides and reducing the volumes of storage tank waste at national sites for final disposal. This paper discusses the separation of the sludge solids and supernate, the basic washing of the sludge solids, the acidic dissolution of the sludge solids, and the removal of the radionuclides from the supernate

  6. Lower Colorado River GRP Leaking Underground Storage Tank Sites (Open), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  7. Lower Colorado River GRP Leaking Underground Storage Tank Sites (Closed), Nevada, 2012, Nevada Division of Environmental Protection Bureau of Corrective Actions

    Data.gov (United States)

    U.S. Environmental Protection Agency — The BCA layers are derived from a database for Federally Regulated Underground Storage Tanks (UST) and a database for Remediation and Leaking Underground Storage...

  8. A new principle for underground pumped hydroelectric storage

    DEFF Research Database (Denmark)

    Olsen, Jan; Paasch, Kasper; Lassen, Benny

    2015-01-01

    cost is movement of soil. A cost analysis indicates that a full scale system will be economically viable when connected to the European power grid where the main revenue will come from selling ancillary services. The storage cost for a full scale 30 MW/200 MWh system is estimated to be approximately 5...

  9. 18 CFR 157.213 - Underground storage field facilities.

    Science.gov (United States)

    2010-04-01

    ... the storage reservoir boundary, as defined by fluid contacts or natural geological barriers; the... REGULATORY COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES... 7 OF THE NATURAL GAS ACT Interstate Pipeline Blanket Certificates and Authorization Under Section 7...

  10. STORAGE AND RECOVERY OF SECONDARY WASTE COMING FROM MUNICIPAL WASTE INCINERATION PLANTS IN UNDERGROUND MINE

    Directory of Open Access Journals (Sweden)

    Waldemar Korzeniowski

    2016-09-01

    Full Text Available Regarding current and planned development of municipal waste incineration plants in Poland there is an important problem of the generated secondary waste management. The experience of West European countries in mining shows that waste can be stored successfully in the underground mines, but especially in salt mines. In Poland there is a possibility to set up the underground storage facility in the Salt Mine “Kłodawa”. The mine today is capable to locate over 3 million cubic meters and in the future it can increase significantly. Two techniques are proposed: 1 – storage of packaged waste, 2 – waste recovery as selfsolidifying paste with mining technology for rooms backfilling. Assuming the processing capacity of the storage facility as 100 000 Mg of waste per year, “Kłodawa” mine will be able to accept around 25 % of currently generated waste coming from the municipal waste incineration plants and the current volume of the storage space is sufficient for more than 20 years. Underground storage and waste recovery in mining techniques are beneficial for the economy and environment.

  11. Underground storage tank 431-D1U1, Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mancieri, S.

    1993-09-01

    This document contains information about the decommissioning of Tank 431-D1U1. This tank was installed in 1965 for diesel fuel storage. This tank will remain in active usage until closure procedures begin. Soils and ground water around the tank will be sampled to check for leakage. Appendices include; proof of proper training for workers, health and safety briefing record, task hazard analysis summary, and emergency plans.

  12. Standard review plan for dry cask storage systems. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    The Standard Review Plan (SRP) For Dry Cask Storage Systems provides guidance to the Nuclear Regulatory Commission staff in the Spent Fuel Project Office for performing safety reviews of dry cask storage systems. The SRP is intended to ensure the quality and uniformity of the staff reviews, present a basis for the review scope, and clarification of the regulatory requirements. Part 72, Subpart B generally specifies the information needed in a license application for the independent storage of spent nuclear fuel and high level radioactive waste. Regulatory Guide 3.61 {open_quotes}Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Cask{close_quotes} contains an outline of the specific information required by the staff. The SRP is divided into 14 sections which reflect the standard application format. Regulatory requirements, staff positions, industry codes and standards, acceptance criteria, and other information are discussed.

  13. Standard review plan for dry cask storage systems. Final report

    International Nuclear Information System (INIS)

    1997-01-01

    The Standard Review Plan (SRP) For Dry Cask Storage Systems provides guidance to the Nuclear Regulatory Commission staff in the Spent Fuel Project Office for performing safety reviews of dry cask storage systems. The SRP is intended to ensure the quality and uniformity of the staff reviews, present a basis for the review scope, and clarification of the regulatory requirements. Part 72, Subpart B generally specifies the information needed in a license application for the independent storage of spent nuclear fuel and high level radioactive waste. Regulatory Guide 3.61 open-quotes Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Caskclose quotes contains an outline of the specific information required by the staff. The SRP is divided into 14 sections which reflect the standard application format. Regulatory requirements, staff positions, industry codes and standards, acceptance criteria, and other information are discussed

  14. Estimating heel retrieval costs for underground storage tank waste at Hanford. Draft

    International Nuclear Information System (INIS)

    DeMuth, S.

    1996-01-01

    Approximately 100 million gallons (∼400,000 m 3 ) of existing U.S. Department of Energy (DOE) owned radioactive waste stored in underground tanks can not be disposed of as low-level waste (LLW). The current plan for disposal of UST waste which can not be disposed of as LLW is immobilization as glass and permanent storage in an underground repository. Disposal of LLW generally can be done sub-surface at the point of origin. Consequently, LLW is significantly less expensive to dispose of than that requiring an underground repository. Due to the lower cost for LLW disposal, it is advantageous to separate the 100 million gallons of waste into a small volume of high-level waste (HLW) and a large volume of LLW

  15. The underground laboratory. A unique scientific tool to design a reversible storage

    International Nuclear Information System (INIS)

    2010-07-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra is carrying out studies on deep reversible waste storage for high-level and long living intermediate-level radioactive wastes thanks to the underground laboratory of its Meuse/Haute-Marne center. This brochure presents the geologic surveys which have led to the selection of the Callovo-Oxfordian argillite formation for the sitting of the underground lab and the underground architecture of the lab. The rock mechanic, heat transfer and rock-fluid interaction experiments carried out in the lab in collaboration with several scientific partners are briefly summarised

  16. The electrostatic properties of Fiber-Reinforced-Plastics double wall underground storage gasoline tanks

    International Nuclear Information System (INIS)

    Li, Yipeng; Liu, Quanzhen; Meng, He; Sun, Lifu; Zhang, Yunpeng

    2013-01-01

    At present Fiber Reinforced Plastics (FRP) double wall underground storage gasoline tanks are wildly used. An FRP product with a resistance of more than 10 11 Ω is a static non-conductor, so it is difficult for the static electricity in the FRP product to decay into the earth. In this paper an experimental system was built to simulate an automobile gasoline filling station. Some electrostatic parameters of the gasoline, including volume charge density, were tested when gasoline was unloaded into a FRP double wall underground storage tank. Measurements were taken to make sure the volume charge density in the oil-outlet was similar to the volume charge density in the tank. In most cases the volume charge density of the gasoline was more than 22.7 μC m −3 , which is likely to cause electrostatic discharge in FRP double wall underground storage gasoline tanks. On the other hand, it would be hard to ignite the vapor by electrostatic discharge since the vapor pressure in the tanks is over the explosion limit. But when the tank is repaired or re-used, the operators must pay attention to the static electricity and some measurements should be taken to avoid electrostatic accident. Besides the relaxation time of charge in the FRP double wall gasoline storage tanks should be longer.

  17. Reducing drinking water supply chemical contamination: risks from underground storage tanks.

    Science.gov (United States)

    Enander, Richard T; Hanumara, R Choudary; Kobayashi, Hisanori; Gagnon, Ronald N; Park, Eugene; Vallot, Christopher; Genovesi, Richard

    2012-12-01

    Drinking water supplies are at risk of contamination from a variety of physical, chemical, and biological sources. Ranked among these threats are hazardous material releases from leaking or improperly managed underground storage tanks located at municipal, commercial, and industrial facilities. To reduce human health and environmental risks associated with the subsurface storage of hazardous materials, government agencies have taken a variety of legislative and regulatory actions--which date back more than 25 years and include the establishment of rigorous equipment/technology/operational requirements and facility-by-facility inspection and enforcement programs. Given a history of more than 470,000 underground storage tank releases nationwide, the U.S. Environmental Protection Agency continues to report that 7,300 new leaks were found in federal fiscal year 2008, while nearly 103,000 old leaks remain to be cleaned up. In this article, we report on an alternate evidence-based intervention approach for reducing potential releases from the storage of petroleum products (gasoline, diesel, kerosene, heating/fuel oil, and waste oil) in underground tanks at commercial facilities located in Rhode Island. The objective of this study was to evaluate whether a new regulatory model can be used as a cost-effective alternative to traditional facility-by-facility inspection and enforcement programs for underground storage tanks. We conclude that the alternative model, using an emphasis on technical assistance tools, can produce measurable improvements in compliance performance, is a cost-effective adjunct to traditional facility-by-facility inspection and enforcement programs, and has the potential to allow regulatory agencies to decrease their frequency of inspections among low risk facilities without sacrificing compliance performance or increasing public health risks. © 2012 Society for Risk Analysis.

  18. Office building with an underground storage system. Operational experiences after one year; Buerogebaeude mit Erdspeicher. Betriebserfahrungen nach einem Jahr

    Energy Technology Data Exchange (ETDEWEB)

    Braun, Dorothee; Wehrli, Stefan [Basler und Hofmann AG, Zuerich (Switzerland)

    2011-07-01

    Self-sufficient heating and cooling - that was the principle of Basler paragraph Hofmann AG (Zuerich, Switzerland) and Stuecheli Architects (Zuerich, Switzerland) in the planning and constructing of a new office building in the Canton of Zuerich. For the first time an underground storage system was implemented in a commercial building. This underground storage refuels the solar energy in summer and supplies heating energy in winter. The office building was settled in in September, 2010. The pioneering project now delivers first empirical values with the underground storage system. These empirical values show: The concept comes up, but needs time.

  19. Considerations for Disposition of Dry Cask Storage System Materials at End of Storage System Life

    International Nuclear Information System (INIS)

    Howard, Rob; Van den Akker, Bret

    2014-01-01

    Dry cask storage systems are deployed at nuclear power plants for used nuclear fuel (UNF) storage when spent fuel pools reach their storage capacity and/or the plants are decommissioned. An important waste and materials disposition consideration arising from the increasing use of these systems is the management of the dry cask storage systems' materials after the UNF proceeds to disposition. Thermal analyses of repository design concepts currently under consideration internationally indicate that waste package sizes for the geologic media under consideration may be significantly smaller than the canisters being used for on-site dry storage by the nuclear utilities. Therefore, at some point along the UNF disposition pathway, there could be a need to repackage fuel assemblies already loaded into the dry storage canisters currently in use. In the United States, there are already over 1650 of these dry storage canisters deployed and approximately 200 canisters per year are being loaded at the current fleet of commercial nuclear power plants. There is about 10 cubic meters of material from each dry storage canister system that will need to be dispositioned. The concrete horizontal storage modules or vertical storage overpacks will need to be reused, re-purposed, recycled, or disposed of in some manner. The empty metal storage canister/cask would also have to be cleaned, and decontaminated for possible reuse or recycling or disposed of, likely as low-level radioactive waste. These material disposition options can have impacts of the overall used fuel management system costs. This paper will identify and explore some of the technical and interface considerations associated with managing the dry cask storage system materials. (authors)

  20. Assessment of feasible strategies for seasonal underground hydrogen storage in a saline aquifer

    Science.gov (United States)

    Sáinz-García, Alvaro; Abarca, Elena; Rubí, Violeta; Grandia, Fidel

    2017-04-01

    Renewable energies are unsteady, which results in temporary mismatches between demand and supply. The conversion of surplus energy to hydrogen and its storage in geological formations is one option to balance this energy gap. This study evaluates the feasibility of seasonal storage of hydrogen produced from wind power in Castilla-León region (northern Spain). A 3D multiphase numerical model is used to test different extraction well configurations during three annual injection-production cycles in a saline aquifer. Results demonstrate that underground hydrogen storage in saline aquifers can be operated with reasonable recovery ratios. A maximum hydrogen recovery ratio of 78%, which represents a global energy efficiency of 30%, has been estimated. Hydrogen upconing emerges as the major risk on saline aquifer storage. However, shallow extraction wells can minimize its effects. Steeply dipping geological structures are key for an efficient hydrogen storage.

  1. The Cigeo project: an industrial storage site for radioactive wastes in deep underground

    International Nuclear Information System (INIS)

    Krieguer, Jean-Marie

    2017-01-01

    In 2006, France has decided to store its high-level and long-lived radioactive wastes, mostly issued from the nuclear industry, in a deep geological underground disposal site. This document presents the Cigeo project, a deep underground disposal site (located in the East of France) for such radioactive wastes, which construction is to be started in 2021 (subject to authorization in 2018). After a brief historical review of the project, started 20 years ago, the document presents the radioactive waste disposal context, the ethical choice of underground storage (in France and elsewhere) for these types of radioactive wastes, the disposal site safety and financing aspects, the progressive development of the underground facilities and, of most importance, its reversibility. In a second part, the various works around the site are presented (transport, buildings, water and power supply, etc.) together with a description of the various radioactive wastes (high and intermediate level and long-lived wastes and their packaging) that will be disposed in the site. The different steps of the project are then reviewed (the initial design and initial construction phases, the pilot industrial phase (expected in 2030), the operating phase, and the ultimate phases that will consist in the definitive closure of the site and its monitoring), followed by an extensive description of the various installations of surface and underground facilities, their architecture and their equipment

  2. Vacuum Drying Tests for Storage of Aluminum Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Chen, K.F.; Large, W.S.; Sindelar, R.L.

    1998-05-01

    A total inventory of up to approximately 32,000 aluminum-based spent nuclear fuel (Al SNF) assemblies are expected to be shipped to Savannah River Site (SRS) from domestic and foreign research reactors over the next several decades. Treatment technologies are being developed as alternatives to processing for the ultimate disposition of Al SNF in the geologic repository. One technology, called Direct/Co-disposal of Al SNF, would place the SNF into a canister ready for disposal in a waste package, with or without canisters containing high-level radioactive waste glass logs, in the repository. The Al SNF would be transferred from wet storage and would need to be dried in the Al SNF canister. The moisture content inside the Al SNF canister is limited to avoid excessive Al SNF corrosion and hydrogen buildup during interim storage before disposal. A vacuum drying process was proposed to dry the Al SNF in a canister. There are two major concerns for the vacuum drying process. One is water inside the canister could become frozen during the vacuum drying process and the other one is the detection of dryness inside the canister. To vacuum dry an irradiated fuel in a heavily shielded canister, it would be very difficult to open the lid to inspect the dryness during the vacuum drying operation. A vacuum drying test program using a mock SNF assembly was conducted to demonstrate feasibility of drying the Al SNF in a canister. These tests also served as a check-out of the drying apparatus for future tests in which irradiated fuel would be loaded into a canister under water followed by drying for storage

  3. Dry-type radioactive material storage facility

    International Nuclear Information System (INIS)

    Yamanaka, Yasuharu; Matsuda, Masami; Kanai, Hidetoshi; Ganda, Takao.

    1996-01-01

    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.)

  4. Flexibility of the BNFL dry storage systems

    International Nuclear Information System (INIS)

    Dickson, R.M.

    1999-01-01

    To widen its range of spent fuel management services, BNFL entered the fuel storage market in 1995; entry was by acquisition rather than internal product development. The need for a transportable product was identified very early, but represents only the first phase of a philosophy of continuous improvement. Strong synergy exists between the new business area and existing fuel handling and transportation expertise, which has been of considerable assistance to the new business. (author)

  5. Regulatory analysis of the Underground Storage Tank-Integrated Demonstration Program

    International Nuclear Information System (INIS)

    Smith, E.H.

    1992-01-01

    The Underground Storage Tank-Integrated Demonstration (UST-ID) Program has been developed to identify, demonstrate, test, and evaluate technologies that will provide alternatives to the current underground storage tank remediation program. The UST-ID Program is a national program that consists of five participating US Department of Energy (DOE) sites where technologies can be developed an ultimately demonstrated. Once these technologies are demonstrated, the UST-ID Program will transfer the developed technology system to industry (governmental or industrial) for application or back to Research and Development for further evaluation and modification, as necessary. In order to ensure that the UST-ID Program proceeds without interruption, it will be necessary to identify regulatory requirements along with associated permitting and notification requirements early in the technology development process. This document serves as a baseline for identifying certain federal and state regulatory requirements that may impact the UST-ID Program and the demonstration of any identified technologies

  6. Large underground radioactive waste storage tanks successfully cleaned at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Billingsley, K.; Burks, B.L.; Johnson, M.; Mims, C.; Powell, J.; Hoesen, D. van

    1998-05-01

    Waste retrieval operations were successfully completed in two large underground radioactive waste storage tanks in 1997. The US Department of Energy (DOE) and the Gunite Tanks Team worked cooperatively during two 10-week waste removal campaigns and removed approximately 58,300 gallons of waste from the tanks. About 100 gallons of a sludge and liquid heel remain in each of the 42,500 gallon tanks. These tanks are 25 ft. in diameter and 11 ft. deep, and are located in the North Tank Farm in the center of Oak Ridge National Laboratory. Less than 2% of the radioactive contaminants remain in the tanks, proving the effectiveness of the Radioactive Tank Cleaning System, and accomplishing the first field-scale cleaning of contaminated underground storage tanks with a robotic system in the DOE complex

  7. Model based, sensor directed remediation of underground storage tanks

    International Nuclear Information System (INIS)

    Christensen, B.; Drotning, W.; Thunborg, S.

    1991-01-01

    Sensor rich, intelligent robots which function with respect to models of their environment have significant potential to reduce the time and cost for the cleanup of hazardous waste while increasing operator safety. Sandia National Laboratories is performing experimental investigations into the application of intelligent robot control technology to the problem of removing waste stored tanks. This paper describes the experimental environment employed at Saudi with particular attention to the computing and software control environment. Intelligent system control is achieved though the integration of extensive geometric and kinematic world models with real-time sensor based control. All operator interactions with the system are validate all operator commands before execution to provide a safe operation. Sensing is used to add information to the robot system's world model and to allow sensor based sensor control during selected operations. The results of a first Critical Feature Test are reported and the potential for applying advanced intelligent control concepts to the removal of waste in storage tanks is discussed

  8. Heat pipe cooling system for underground, radioactive waste storage tanks

    International Nuclear Information System (INIS)

    Cooper, K.C.; Prenger, F.C.

    1980-02-01

    An array of 37 heat pipes inserted through the central hole at the top of a radioactive waste storage tank will remove 100,000 Btu/h with a heat sink of 70 0 F atmospheric air. Heat transfer inside the tank to the heat pipe is by natural convection. Heat rejection to outside air utilizes a blower to force air past the heat pipe condenser. The heat pipe evaporator section is axially finned, and is constructed of stainless steel. The working fluid is ammonia. The finned pipes are individually shrouded and extend 35 ft down into the tank air space. The hot tank air enters the shroud at the top of the tank and flows downward as it is cooled, with the resulting increased density furnishing the pressure difference for circulation. The cooled air discharges at the center of the tank above the sludge surface, flows radially outward, and picks up heat from the radioactive sludge. At the tank wall the heated air rises and then flows inward to comple the cycle

  9. FRAPCON analysis of cladding performance during dry storage operations

    Directory of Open Access Journals (Sweden)

    David J. Richmond

    2018-03-01

    Full Text Available There is an increasing need in the United States and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations or interim storage sites. Under normal conditions, the Nuclear Regulatory Commission limits cladding temperature to 400°C for high-burnup (>45 GWd/mtU fuel, with higher temperatures allowed for low-burnup fuel. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at 400°C. Results were representative of the majority of US light water reactor fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage. Keywords: Dry Storage, FRAPCON, Fuel Performance, Radial Hydride Reorientation, Vacuum Drying

  10. New concept for ARS dry spent fuel storage

    International Nuclear Information System (INIS)

    Doroszlai, P.G.K.; Johanson, N.W.; Patak, H.N.

    1980-01-01

    The dry fully passive and modular away-from-reactor (AFR) storage concept has been presented before for a size of 1500 to 3000 MTHM. Here it is suggested that the same concept is applicable for a small AR storage facility of 200 MTHM. Detailed investigations and feasibility studies have shown this concept to be economically interesting. Dry storage in the proposed concept has some other inherent advantages: spent fuel is stored in a dry and inert atmosphere, where no corrosion nor determination of cladding is to be expected during extended storage periods; storage canister and the silo concrete are additional barriers against activity release and increase therefore the security for long term safety; there are only passive systems involved where the heat is dissipated by natural convection and there is no need for additional emergency systems or special redundancy; concept of AR storage should be relatively easily licensed, as all requirements or constructions are well known standards of engineering; this storage concept creates no secondary waste nor contamination making decomissioning simple after retransfer of spent fuel canisters; manpower requirements for operation and maintenance is very small; operating costs are estimated to be some 2 US $/kg U (1980); investment costs are calculated to be 96 US $/kg U (May 1980) for a total size of 200 MTHM stored

  11. High water level installation of monitoring wells for underground storage tanks

    International Nuclear Information System (INIS)

    Treadway, C.

    1990-01-01

    This paper briefly describes a common monitoring well installation design for shallow ground water contamination resulting from leaky underground storage tanks. The paper describes drilling techniques used in unconsolidated Florida aquifers using hollow-stem augers. It describes methods for the prevention of heaving sands and sand-locking problems. It then goes on to describe the proper well casing placement and sealing techniques using neat cements. The proper sell screen level is also discussed to maximize the detection of floating hydrocarbons

  12. RECOMMENDATIONS ON THE MONITORING SYSTEM OF UNDERGROUND GAS STORAGE (in Russian

    Directory of Open Access Journals (Sweden)

    Victor NORDIN

    2014-07-01

    Full Text Available The article in accordance with the "process approach" ISO 9000 is substantiated the necessity of creating underground gas storage system monitoring and control, including objects, parameters, methods, frequency and corrective action, on the basis of which made structural formula monitoring cycle. Qualimetrical approach allows to define complex criteria of an estimation of efficiency of operation, which will help to make timely and effective management decisions, including from the perspective of environmental protection.

  13. Underground storage with floating cover. An overview; Erdbeckenspeicher mit schwimmender Abdeckung. Eine Uebersicht

    Energy Technology Data Exchange (ETDEWEB)

    Heller, A.; Maureschat, G.; Duer, K. [Technical Univ. of Denmark, Lyngby (Denmark). Dept. of Buildings and Energy

    1998-12-31

    A number of underground stores have been developed in recent years in Denmark. The development has been subsidised with funds of `Development program renewable energy` launched by the Danish Ministry for Environment and Energy. First experience reports on underground storage show that more emphasis must be put on the development of storage sealing and cover construction. Hence research works currently focuses on the investigation of liner material and further development of floating cover constructions. The target is the development of underground storage using solar energy for heating that can compete with conventional heating systems technically and economically. (orig.) [Deutsch] In Daenemark hat man in den letzten Jahren eine Reihe von Erdbeckenspeichern entwickelt. Die Entwicklung wird mit Mitteln aus dem `Entwicklungsprogramm Erneuerbare Energie` vom daenischen Umwelt- und Energieministerium finanziell gefoerdert. Die ersten Erfahrungen mit Erdbeckenspeichern haben gezeigt, dass ein verstaerkter Einsatz bei der Entwicklung von Abdichtungen des Speichers und von Deckelkonstruktionen gefordert ist. Deshalb wird in Daenemark aktuell mit der Untersuchung von Linermaterialien und der Weiterentwicklung von schwimmenden Deckelkonstruktionen gearbeitet. Das Ziel dieser Arbeit ist es, Erdbeckenspeicher zu entwickeln, die die Ausnutzung von Sonnenenergie zur Waermeversorgung im Vergleich mit herkoemmlicher Waermeversorgung sowohl technisch als auch oekonomisch konkurrenzfaehig macht. (orig.)

  14. Safety assessment of OPG's used fuel for dry storage

    International Nuclear Information System (INIS)

    Roman, H.; Khan, A.

    2005-01-01

    'Full text:' Ontario Power Generation (OPG) operates the Pickering Waste Management Facility (PWMF) and Western Waste Management Facility (WWMF) where OPG has been storing 10-year or older used fuel in the Dry Storage Containers (DSCs) since 1996 and 2003 respectively. The construction licence for the Darlington Used Fuel Dry Storage Facility (DUFDSF) was obtained in August 2004. Safety assessment of the used fuel for dry storage is required to support each request for regulatory approval to construct and operate a dry storage facility. The objective of the safety assessment is to assess the used fuel performance under normal operation and postulated credible accident scenarios. A reference used fuel bundle is defined based on the operating history and data on fuel discharged from the reactors of the specific nuclear generating station. The characteristics of the reference used fuel bundle are used to calculate the nuclide inventory, source term and decay heat used for the assessment. When assessing malfunctions and accidents, postulated external and internal events are considered. Consideration is also given to the design basis accidents of the specific nuclear generating station that could affect the used fuel under dry storage. For those events deemed credible (i.e. probability > 10 -7 ), a bounding fuel failure consequence is predicted. Given the chemical characteristics of the radionuclides in used fuel, the design of the CANDU fuel and the conditions inside the DSC, in the event that a used fuel bundle should become damaged during used fuel dry storage operations, the only significant radionuclides species that are volatile are krypton-85 and tritium. Release of these radionuclides is considered in calculating public and worker doses. (author)

  15. Dry spent fuel storage in the 1990's

    International Nuclear Information System (INIS)

    Roberts, J.P.

    1991-01-01

    In the US, for the decade of the 1990's, at-reactor-site dry spent fuel storage has become the predominant option outside of reactor spent fuel pools. This development has resulted from failure, in the 1980's, of a viable reprocessing option for commercial power reactors, and delay in geologic repository development to an operational date at or beyond the year 2010. Concurrently, throughout the 1980's, aggressive technical and regulatory efforts by the Federal Government, coordinated with nuclear industry, have led to successful evolution of dry spent fuel storage as a utility option

  16. Spent fuel dry storage experience at Gentilly 2 NGS

    International Nuclear Information System (INIS)

    Macici, N.

    1997-01-01

    In order to provide the needed interim storage facility for the spent fuel, Hydro-Quebec chose the dry storage CANSTOR module developed by the Atomic Energy of Canada Ltd (AECL). The decision was made based upon the technical feasibility, public and environmental protection criteria, operational flexibility, economic and space saving advantages. Before the commissioning of the spent fuel dry storage facility, the project received all the required approvals. A joint provincial - federal public hearings was held in summer of 1994 in order to assess the project in term of its impact on the environment. In September 1995 took place the first transfer of spent fuel from the station bay to the dry storage facility and since then 21000 bundles of spent fuel were transferred in the two CANSTOR modules built on the station site located within the protected area of the Gentilly-2 station. To date, the expected performance of the dry storage units and equipment have been met. A third CANSTOR module is to be built in summer of 1997 on the station site. (author)

  17. A research on the excavation and maintenance of underground energy storage

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Hee-Soon; Chung, So-Keul; Ryu, Chang-Ha [Korea Institute of Geology Mining and Materials, Taejon (KR)] (and others)

    1999-12-01

    CAES which is called as a compressed air energy storage was firstly developed at Huntorf, Gen-nan in 1978. The capacity of that system was 290MW, and it can be treated as a first commercial power plant. CAES has a lot of merits, such as saving the unit price of power generation, averaging the peak demand, improvement of maintenance, enlarging the benefit of dynamic use. According to the literature survey, the unlined rock cavern should be proposed to be a reasonable storing style as a method of compressed air storage in Korea. In this study, the most important techniques were evaluated through the investigation of the foreign construction case studies, especially on the unlined rock caverns in hard rock mass. We decided the hill of the Korea Institute of Geology, Mining and Materials as CAES site. If we construct the underground spaces in this site, the demand for electricity nearby Taejon should be considered. So we could determine the capacity of the power plant as a 350MW. This capacity needs a underground space of 200,000, and we can conclude 4 parallel tunnels 550m deep from the surface through the numerical studies. Design parameters were achieved from 300m depth boring job and image processing job. Moreover the techniques for determination of joint characteristics from the images could be obtained. Blasting pattern was designed on the underground spaces, and automatic gas control system and thermomechanical characteristics on caverns were also studied. And finally the following research items could be proposed for future researches. (1) Establishment of criteria for selection of optimal tunnel type. (2) Evaluation of water tightening ability. (3) Investigation of Lining type. (4) Development of techniques for site investigation in deep underground project. (5) Evaluation of construction techniques for underground space and shaft. (6) Investigation of long-term maintenance for pressured tunnel. (author). 14 refs.

  18. Advantages of dry hardened cask storage over wet storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio, E-mail: romanato@ctmsp.mar.mil.b [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade

    2011-07-01

    Pools are generally used to store and maintain spent nuclear fuel assemblies for cooling, after removed from reactors. After three to five years stored in the pools, spent fuel can be reprocessed or sent to a final disposition in a geological repository and handled as radioactive waste or sent to another site waiting for future solution. Spent fuel can be stored in dry or wet installations, depending on the method adopted by the nuclear plant. If this storage were exclusively wet, at the installation decommissioning in the future, another solution for storage will need to be found. Today, after a preliminary cooling, the spent fuel assemblies can be removed from the pool and sent to dry hardened storage installations. This kind of storage does not need complex radiation monitoring and it is safer than wet storage. Brazil has two nuclear reactors in operation, a third reactor is under construction and they use wet spent fuel storage . Dry hardened casks use metal or both metal and concrete for radiation shielding and they are safe, especially during an earthquake. An earthquake struck Japan on March 11, 2011 damaging Fukushima Daiichi nuclear power plant. The occurrence of earthquakes in Brazil is very small but dry casks can resist to other events, including terrorist acts, better than pools. This paper shows the advantages of dry hardened cask storage in comparison with the wet storage (water pools) for spent nuclear fuel. (author)

  19. Advantages of dry hardened cask storage over wet storage for spent nuclear fuel

    International Nuclear Information System (INIS)

    Romanato, Luiz Sergio

    2011-01-01

    Pools are generally used to store and maintain spent nuclear fuel assemblies for cooling, after removed from reactors. After three to five years stored in the pools, spent fuel can be reprocessed or sent to a final disposition in a geological repository and handled as radioactive waste or sent to another site waiting for future solution. Spent fuel can be stored in dry or wet installations, depending on the method adopted by the nuclear plant. If this storage were exclusively wet, at the installation decommissioning in the future, another solution for storage will need to be found. Today, after a preliminary cooling, the spent fuel assemblies can be removed from the pool and sent to dry hardened storage installations. This kind of storage does not need complex radiation monitoring and it is safer than wet storage. Brazil has two nuclear reactors in operation, a third reactor is under construction and they use wet spent fuel storage . Dry hardened casks use metal or both metal and concrete for radiation shielding and they are safe, especially during an earthquake. An earthquake struck Japan on March 11, 2011 damaging Fukushima Daiichi nuclear power plant. The occurrence of earthquakes in Brazil is very small but dry casks can resist to other events, including terrorist acts, better than pools. This paper shows the advantages of dry hardened cask storage in comparison with the wet storage (water pools) for spent nuclear fuel. (author)

  20. Quality of second season soybean submitted to drying and storage

    Directory of Open Access Journals (Sweden)

    Cesar Pedro Hartmann Filho

    2016-09-01

    Full Text Available Drying agricultural products reduces the moisture content to suitable levels for storage, in order to maintain the product quality. However, special care with the temperatures applied in the process is important for the integrity and longevity of the material. The present study aimed at determining the immediate and latent effect of air-drying temperatures on the quality of soybean produced as a second season crop. The grains were collected at the R8 stage, close to the physiological maturity, with moisture content of approximately 23 % (w.b., submitted to drying temperatures of 40 ºC, 50 ºC, 60 ºC, 70 ºC and 80 ºC, up to a moisture content of 12.5 ± 0.7 % (w.b., and then stored under non-controlled humidity and temperature for 180 days. Thereafter, quality was assessed every 45 days by determining the dry matter loss, color and crude protein and lipid contents, as well as the acidity and peroxide indices of the crude oil extracted. Based on the results obtained, it was concluded that the increase in the air-drying temperature affects the soybean quality and crude oil extracted, being this effect enhanced with the storage time; the soybean and crude oil quality decline with an increase in the air-drying temperature and storage time; the air temperature of 40 ºC has the least effect on the quality of soybean grains and crude oil extracted.

  1. A GIS-based 3D online information system for underground energy storage in northern Germany

    Science.gov (United States)

    Nolde, Michael; Malte, Schwanebeck; Ehsan, Biniyaz; Rainer, Duttmann

    2015-04-01

    We would like to present the concept and current state of development of a GIS-based 3D online information system for underground energy storage. Its aim is to support the local authorities through pre-selection of possible sites for thermal, electrical and substantial underground energy storages. Since the extension of renewable energies has become legal requirement in Germany, the underground storing of superfluously produced green energy (such as during a heavy wind event) in the form of compressed air, gas or heated water has become increasingly important. However, the selection of suitable sites is a complex task. The presented information system uses data of geological features such as rock layers, salt domes and faults enriched with attribute data such as rock porosity and permeability. This information is combined with surface data of the existing energy infrastructure, such as locations of wind and biogas stations, powerline arrangement and cable capacity, and energy distribution stations. Furthermore, legal obligations such as protected areas on the surface and current underground mining permissions are used for the process of pre-selecting sites suitable for energy storage. Not only the current situation but also prospective scenarios, such as expected growth in produced amount of energy are incorporated in the system. While the process of pre-selection itself is completely automated, the user has full control of the weighting of the different factors via the web interface. The system is implemented as an online 3D server GIS environment, so that it can easily be utilized in any web browser. The results are visualized online as interactive 3d graphics. The information system is implemented in the Python programming language in combination with current Web standards, and is build using only free and open source software. It is being developed at Kiel University as part of the ANGUS+ project (lead by Prof. Sebastian Bauer) for the federal state of

  2. Dry Storage of Research Reactor Spent Nuclear Fuel - 13321

    Energy Technology Data Exchange (ETDEWEB)

    Adams, T.M.; Dunsmuir, M.D.; Leduc, D.R.; Severynse, T.F.; Sindelar, R.L. [Savannah River National Laboratory (United States); Moore, E.N. [Moore Nuclear Energy, LLC (United States)

    2013-07-01

    Spent fuel from domestic and foreign research reactors is received and stored at the Savannah River Site's L Area Material Storage (L Basin) Facility. This DOE-owned fuel consists primarily of highly enriched uranium in metal, oxide or silicide form with aluminum cladding. Upon receipt, the fuel is unloaded and transferred to basin storage awaiting final disposition. Disposition alternatives include processing via the site's H Canyon facility for uranium recovery, or packaging and shipment of the spent fuel to a waste repository. A program has been developed to provide a phased approach for dry storage of the L Basin fuel. The initial phase of the dry storage program will demonstrate loading, drying, and storage of fuel in twelve instrumented canisters to assess fuel performance. After closure, the loaded canisters are transferred to pad-mounted concrete overpacks, similar to those used for dry storage of commercial fuel. Unlike commercial spent fuel, however, the DOE fuel has high enrichment, very low to high burnup, and low decay heat. The aluminum cladding presents unique challenges due to the presence of an oxide layer that forms on the cladding surface, and corrosion degradation resulting from prolonged wet storage. The removal of free and bound water is essential to the prevention of fuel corrosion and radiolytic generation of hydrogen. The demonstration will validate models predicting pressure, temperature, gas generation, and corrosion performance, provide an engineering scale demonstration of fuel handling, drying, leak testing, and canister backfill operations, and establish 'road-ready' storage of fuel that is suitable for offsite repository shipment or retrievable for onsite processing. Implementation of the Phase I demonstration can be completed within three years. Phases II and III, leading to the de-inventory of L Basin, would require an additional 750 canisters and 6-12 years to complete. Transfer of the fuel from basin storage

  3. Commercial solutions [for dry spent fuel storage casks

    International Nuclear Information System (INIS)

    Howe, W.F.; Pennington, C.W.; Hobbs, J.; Lee, W.; Thomas, B.D.; Dibert, D.J.

    1996-01-01

    In the aftermath of the termination of the DOE's MPC (Multi-Purpose Canister) programme, commercial suppliers are coming forward with new or updated systems to meet utility needs. Leading vendors describe the advantages of their systems for dry spent fuel storage and transport. (Author)

  4. Heritability, combining ability and inheritance of storage root dry ...

    African Journals Online (AJOL)

    Storage root dry matter content (RDM) is central to the improvement of consumer and industrial attributes of root crops. Yam bean (Pachyrhizus species) is a legume root crop newly introduced in Uganda, but its adoption may be constrained by low RDM. The objective of this study was to investigate the magnitude of ...

  5. Mines as lower reservoir of an UPSH (Underground Pumping Storage Hydroelectricity): groundwater impacts and feasibility

    Science.gov (United States)

    Bodeux, Sarah; Pujades, Estanislao; Orban, Philippe; Dassargues, Alain

    2016-04-01

    The energy framework is currently characterized by an expanding use of renewable sources. However, their intermittence could not afford a stable production according to the energy demand. Pumped Storage Hydroelectricity (PSH) is an efficient possibility to store and release electricity according to the demand needs. Because of the topographic and environmental constraints of classical PSH, new potential suitable sites are rare in countries whose topography is weak or with a high population density. Nevertheless, an innovative alternative is to construct Underground Pumped Storage Hydroelectricity (UPSH) plants by using old underground mine works as lower reservoir. In that configuration, large amount of pumped or injected water in the underground cavities would impact the groundwater system. A representative UPSH facility is used to numerically determine the interactions with surrounding aquifers Different scenarios with varying parameters (hydrogeological and lower reservoir characteristics, boundaries conditions and pumping/injection time-sequence) are computed. Analysis of the computed piezometric heads around the reservoir allows assessing the magnitude of aquifer response and the required time to achieve a mean pseudo-steady state under cyclic solicitations. The efficiency of the plant is also evaluated taking the leakage into the cavity into account. Combining these two outcomes, some criterions are identified to assess the feasibility of this type of projects within potential old mine sites from a hydrogeological point of view.

  6. Nuclear spent fuel dry storage in the EWA reactor shaft

    International Nuclear Information System (INIS)

    Mieleszczenko, W.; Moldysz, A.; Hryczuk, A.; Matysiak, T.

    2001-01-01

    The EWA reactor was in operation from 1958 until February 1995. Then it was subjected to the decommissioning procedure. Resulting from a prolonged operation of Polish research reactors a substantial amount of nuclear spent fuel of various types, enrichment and degree of burnup have been accumulated. The technology of storage of spent nuclear fuel foresees the two stages of wet storing in a water pool (deferral period from tens to several dozens years) and dry storing (deferral period from 50 to 80 years). In our case the deferral time in the water environment is pretty significant (the oldest fuel elements have been stored in water for more than 40 years). Though the state of stored fuel elements is satisfactory, there is a real need for changing the storage conditions of spent fuel. The paper is covering the description of philosophy and conceptual design for construction of the spent fuel dry storage in the decommissioned EWA reactor shaft. (author)

  7. Safety Test Report for the SNF Dry Storage System

    Energy Technology Data Exchange (ETDEWEB)

    Bang, K. S.; Seo, K. S.; Lee, J. H.; Lee, J. C.; Choi, W. S

    2008-11-15

    This is technical report conducted by KAERI under the contract with NETEC for safety test for the PWR S/F dry storage system. Leak Test was performed after drop test and turn-over test, the measured leakage rate was lower than allowable leakage rate. It is revealed that the containment integrity of the dry storage system is maintained. In the seismic test, the moving of the model was measured at SRTH seismic response of 0.4 g and 0.8 g. Therefore the seismic test results can be used fully to the test data for verification of the seismic analysis. In the thermal test, the direction of the inlet and outlet of the air has no effect on the heat transfer performance. The passive heat removal system of the horizontal storage module was designed well.

  8. Spent LWR fuel encapsulation and dry storage demonstration

    International Nuclear Information System (INIS)

    Bahorich, R.J.; Durrill, D.C.; Cross, T.E.; Unterzuber, R.

    1980-01-01

    In 1977 the Spent Fuel Handling and Packaging Program (SFHPP) was initiated by the Department of Energy to develop and test the capability to satisfactorily encapsulate typical spent fuel assemblies from commercial light-water nuclear power plants and to establish the suitability of one or more surface and near surface concepts for the interim dry storage of the encapsulated spent fuel assemblies. The E-MAD Facility at the Nevada Test Site, which is operated for the Department of Energy by the Advanced Energy Systems Division (AESD) of the Westinghouse Electric Corporation, was chosen as the location for this demonstration because of its extensive existing capabilities for handling highly radioactive components and because of the desirable site characteristics for the proposed storage concepts. This paper describes the remote operations related to the process steps of handling, encapsulating and subsequent dry storage of spent fuel in support of the Demonstration Program

  9. Design and operation problems related to water curtain system for underground water-sealed oil storage caverns

    Directory of Open Access Journals (Sweden)

    Zhongkui Li

    2016-10-01

    Full Text Available The underground water-sealed storage technique is critically important and generally accepted for the national energy strategy in China. Although several small underground water-sealed oil storage caverns have been built in China since the 1970s, there is still a lack of experience for large-volume underground storage in complicated geological conditions. The current design concept of water curtain system and the technical instruction for system operation have limitations in maintaining the stability of surrounding rock mass during the construction of the main storage caverns, as well as the long-term stability. Although several large-scale underground oil storage projects are under construction at present in China, the design concepts and construction methods, especially for the water curtain system, are mainly based on the ideal porosity medium flow theory and the experiences gained from the similar projects overseas. The storage projects currently constructed in China have the specific features such as huge scale, large depth, multiple-level arrangement, high seepage pressure, complicated geological conditions, and high in situ stresses, which are the challenging issues for the stability of the storage caverns. Based on years' experiences obtained from the first large-scale (millions of cubic meters underground water-sealed oil storage project in China, some design and operation problems related to water curtain system during project construction are discussed. The drawbacks and merits of the water curtain system are also presented. As an example, the conventional concept of “filling joints with water” is widely used in many cases, as a basic concept for the design of the water curtain system, but it is immature. In this paper, the advantages and disadvantages of the conventional concept are pointed out, with respect to the long-term stability as well as the safety of construction of storage caverns. Finally, new concepts and principles

  10. Licensing of spent fuel dry storage and consolidated rod storage: A Review of Issues and Experiences

    Energy Technology Data Exchange (ETDEWEB)

    Bailey, W.J.

    1990-02-01

    The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs.

  11. High-temperature acquifer thermal storage and underground heat storage; IEA ECES Annex 12: Hochtemperatur-Erdwaermesonden- und Aquiferwaermespeicher

    Energy Technology Data Exchange (ETDEWEB)

    Sanner, B.; Knoblich, K. [Giessen Univ. (Germany). Inst. fuer Angewandte Geowissenschaften; Koch, M.; Adinolfi, M. [Stuttgart Univ. (Germany). Inst. fuer Siedlungswasserbau, Wasserguete und Abfallwirtschaft

    1998-12-31

    Heat storage is essential for the reconciliation of heat supply and demand. The earth has already proved to be an excellent medium for storing large amounts of heat over longer periods of time, for instance during the cold and hot season. The efficiency of the storage is the better the lower storage losses are at high temperature levels. Unfortunately this can not be easily achieved. While thermal underground stores, which are widely used for cold storage, have proved to perform quite well at temperatures between 10 C - 40 C, it has been rather difficult to achieve similar results at higher temperatures up to 150 C as test and demonstration plants of the 1980s proved. This issue has again attracted so much interest that the IEA launched a project on high temperature underground storage in December 1998. (orig.) [Deutsch] Waermespeicherung ist von entscheidender Bedeutung, wenn es darum geht, ein Waermeangebot mit einer Waermenachfrage zeitlich zur Deckung zu bringen. Der Untergrund hat sich schon seit vielen Jahren als ein geeignetes Medium erwiesen, groessere Waermepumpen ueber laengere Zeitraeume wie etwa die kalten und warmen Jahreszeiten zu speichern. Die Effizienz eines solchen Speichers steigt mit der Hoehe des erreichten Temperaturniveaus und mit sinkenden Speicherverlusten, was leider eher gegenlaeufige Erscheinungen sind. Waehrend thermische Untergrundspeicher im Temperaturbereich von 10-40 C inzwischen erfolgreich demonstriert wurden und vor allem zur Kaeltespeicherung auch bereits vielfach eingesetzt werden, haben hoehere Temperaturen bis etwa 150 C in den Versuchs- und Demonstrationsanlagen der 80er Jahre vielfaeltige Probleme bereitet. Im Gefolge eines erneuten Interesses an unterirdischer thermischer Energiespeicherung wurde im Dezember 1997 ein Vorhaben des IEA Energiespeicherprogramms zu Untergrund-Waermespeichern hoeherer Temperatur eingerichtet. (orig.)

  12. Activity release during the dry storage of fuel assemblies

    International Nuclear Information System (INIS)

    Valentine, M.K.; Fettel, W.; Gunther, H.

    1991-01-01

    This paper reports that wet storage is the predominant storage method in the USA for spent fuel assemblies. Nevertheless, most utilities have stretched their storage capacities and several reactors will lose their full-core reserve in the 90's. A great variety of out-of-pool storage methods already exist, including the FUELSTOR vault-type dry storage concept. A FUELSTOR vault relies on double containment of the spent fuel (intact cladding as the primary containment and sealing of assemblies in canisters filled with an inert gas as the secondary containment) to reduce radiation levels at the outside wall of the vault to less than site boundary levels. Investigation of accident scenarios reveals that radiation release limits are only exceeded following complete failure of all canisters and simultaneous cladding breach for more than 40% of the rods (or for more than 1% of failed rods if massive fuel oxidation occurs following cladding failure). Such failures are considered highly improbable. Thus, it can be concluded that this type of dry storage is safe and individual canister monitoring is not required in the facility

  13. Underground storage at Saint-Illiers-la-Ville. Initial results of filling. Reservoir control problems

    Energy Technology Data Exchange (ETDEWEB)

    Vernet, D

    1968-01-01

    The underground storage at Saint-Illiers-la-Ville (Yvelines in the Paris area) was discussed by Toche at the time when it was filled with gas in 1965. Now, 2-1/2 yr after the initial input, the volume of storage has reached 500 million cu m, and the first industrial withdrawals took place during the winter of 1967-1968. The results obtained in the operation of this underground storage are extremely satisfactory. In spite of differences in the composition of the sand layer, the gas bubble developed in a very regular way, horizontally and vertically, and the full penetration well equipment made a high output rate easy to obtain. Reservoir control was handled efficiently and the movements of the bubble contour were shown for every fluctuation of the injection and withdrawal volumes. Tests for production capacity showed the low extent to which the wells were affected by the phenomenon of water- coning and indicated measures to be taken to prevent the formation of hydrates. The measures effected and the conclusions which can be derived are discussed.

  14. Spent Fuel Transfer to Dry Storage Using Unattended Monitoring System

    International Nuclear Information System (INIS)

    Park, Jae Hwan; Park, Soo Jin

    2009-01-01

    There are 4 CANDU reactors at Wolsung site together with a spent fuel dry storage associated with unit 1. These CANDU reactors, classified as On-Load Reactor (OLR) for Safeguards application, change 16- 24 fuel bundles with fresh fuel in everyday. Especially, the spent fuel bundles are transferred from spent fuel bays to dry storage throughout a year because of the insufficient capacity of spent fuel pond. Safeguards inspectors verify the spent fuel transfer to meet safeguards purposes according to the safeguards criteria by means of inspector's presence during the transfer campaign. For the verification, 60-80 person-days of inspection (PDIs) are needed during approximately 3 months for each unit. In order to reduce the inspection effort and operators' burden, an Unattended Monitoring System (UMS) was designed and developed by the IAEA for the verification of spent fuel bundles transfers from wet storage to dry storage. Based on the enhanced cooperation of CANDU reactors between the ROK and the IAEA, the IAEA installed the UMS at Wolsung unit 2 in January 2005 at first. After some field trials during the transfer campaign, this system is being replaced the traditional human inspection since September 1, 2006 combined with a Short Notice Inspection (SNI) and a near-real time Mailbox Declaration

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

    International Nuclear Information System (INIS)

    Goehring, R.; Stoev, M.; Davis, N.; Thomas, E.

    2004-01-01

    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)

  16. Neutronic and thermal hydraulic of dry cask storage systems

    International Nuclear Information System (INIS)

    Yavuz, U.

    2000-01-01

    Interim spent fuel storage systems must provide for the safe receipt, handling, retrieval and storage of spent nuclear fuel before reprocessing or disposal. In the context of achieving these objectives, the following features of the design are to be taken into consideration: to maintain fuel subcritical, to remove spent fuel residualheat, and to provide for radiation protection. These features in the design of a dry cask storage system were analyzed for normal operating conditions by employing COBRA-SFS, SCALE4.4 (ORIGEN, XSDOSE, CSAS6) codes. For a metal-shielded type storage system, appropriate designs, in accordance with safety assurance limits of IAEA, were obtained for spent fuel burned to 33000, 45000 and 55000 MW d/t and cooled for 5 and 10 years

  17. Modular vault dry storage system for interim storage of irradiated fuel

    International Nuclear Information System (INIS)

    Cundill, B.R.; Ealing, C.J.; Agarwal, B.K.

    1988-01-01

    The Foster Wheeler Energy Application (FWEA) Modular Vault Dry Store (MVDS) is a dry storage concept for the storage of all types of irradiated reactor fuel. For applications in the US, FWEA submitted an MVDS Topical Report to the US NRC during 1986. Following NRC approval of the MVDS Topical Report concept for unconsolidated LWR fuel, US utilities have available a new, compact, economic and flexible system for the storage of irradiated fuel at the reactor site for time periods of at least 20 years (the period of the first license). The MVDS concept jointly developed by FWEA and GEC in the U.K., has other applications for large central away from reactor storage facilities such as a Monitorable Retrievable Storage (MRS) installation. This paper describes the licensed MVDS design, aspects of performance are discussed and capital costs compared with alternative concepts. Alternative configurations of MVDS are outlined

  18. Safe dry storage of intermediate-level waste at CRL

    International Nuclear Information System (INIS)

    Chiu, A.; Sanderson, T.; Lian, J.

    2011-01-01

    Ongoing operations at Atomic Energy of Canada Limited's (AECL) Chalk River Laboratories (CRL) generate High-, Intermediate- and Low-Level Waste (HLW, ILW and LLW) that will require safe storage for several decades until a long-term management facility is available. This waste is stored in below grade concrete structures (i.e. tile holes or bunkers) or the above-ground Shielded Modular Above Ground Storage (SMAGS) facility depending on the thermal and shielding requirements of the particular waste package. Existing facilities are reaching their capacity and alternate storage is required for the future storage of this radioactive material. To this end, work has been undertaken at CRL to design, license, construct and commission the next generation of waste management facilities. This paper provides a brief overview of the existing radioactive-waste management facilities used at CRL and focuses on the essential requirements and issues to be considered in designing a new waste storage facility. Fundamentally, there are four general requirements for a new storage facility to dry store dry non-fissile ILW. They are the need to provide: (1) containment, (2) shielding, (3) decay heat removal, and (4) ability to retrieve the waste for eventual placement in an appropriate long-term management facility. Additionally, consideration must be given to interfacing existing waste generating facilities with the new storage facility. The new facilities will be designed to accept waste for 40 years followed by 60 years of passive storage for a facility lifespan of 100 years. The design should be modular and constructed in phases, each designed to accept ten years of waste. This strategy will allow for modifications to subsequent modules to account for changes in waste characteristics and generation rates. Two design concepts currently under consideration are discussed. (author)

  19. Underground Pumped Hydroelectric Storage (UPHS). Program report, April 1-September 30, 1979. ANL Activity No. 49964

    Energy Technology Data Exchange (ETDEWEB)

    Blomquist, C.A.; Frigo, A.A.; Tam, S.W.; Clinch, J.M.

    1979-10-01

    The Argonne National Laboratory Underground Pumped Hydroelectric Storage activities for the second half of FY 1979 are described. Activities include program management and support, subcontract work, and systems studies. Information is given on the preliminary design, hydraulic performance, and cost of high-head, 350-MW capacity, single- and two-stage reversible, Francis-type pump turbines. Similar information is also presented on 350- and 500-MW capacity, multistage, unregulated, reversible, pump turbines. An assessment of the application potential of controlled-flow rate pumps and pump turbines is included. The effects of the charge/discharge ratio of a pumped stoage plant is also discussed.

  20. Tank Waste Remediation System Inactive Miscellaneous Underground Storage Tanks Program Plan

    International Nuclear Information System (INIS)

    Gustavson, R.D.

    1995-12-01

    The Program Management Plan (PMP) describes the approach that will be used to manage the Tank Waste Remediation System (TWRS) Inactive Miscellaneous Underground Storage Tank (IMUST) Program. The plan describes management, technical, and administrative control systems that will be used to plan and control the IMUSTs Program performance. The technical data to determine the IMUSTs status for inclusion in the Single Shell Tank Farm Controlled Clean and Stable (CCS) Program. The second is to identify and implement surveillance, characterization, stabilization, and modifications to support CCS prior to final closure

  1. Closure Report for Underground Storage Tank 2310-U at the Pine Ridge West Repeater Station

    International Nuclear Information System (INIS)

    1994-07-01

    This document represents the Closure Report for Underground Storage Tank (UST) 2310-U at the Pine Ridge West Repeater Station, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2310-U was a 200-gal gasoline UST which serviced the emergency generator at the Repeater Station. The tank was situated in a shallow tank bay adjacent to the Repeater Station along the crest of Pine Ridge. The tank failed a tightness test in October 1989 and was removed in November 1989. The purpose of this report is to document completion of soil corrective action, present supporting analytical data, and request closure for this site

  2. Efficiency and impacts of hythane (CH4+H2) underground storage

    Science.gov (United States)

    Sáinz-García, Alvaro; Abarca, Elena; Grandia, Fidel

    2016-04-01

    The foreseen increase share of renewable energy production requires energy storage to mitigate shortage periods of energy supply. Hydrogen is an efficient energy carrier that can be transported and storage. A very promising way to store large amounts of hydrogen is underground geological reservoirs. Hydrogen can be stored, among other options, as a mixture of natural gas and less than 20% of hydrogen (hythane) to avoid damages on the existing infrastructure for gas transport. This technology is known as power-to-gas and is being considered by a number of European countries (Simon et al., 2015). In this study, the feasibility of a deep aquifer to store CH4-H2 mixtures in the Lower Triassic of the Paris Basin is numerically analyzed. The solubility of gas mixture in the groundwater is extremely low (Panfilov, 2015) and, therefore, gas and water are considered immiscible and non-reactive. An immiscible multiphase flow model is developed using the coefficient-form PDE interface of the finite element method code, COMSOL Multiphysics. The modelled domain is a 2D section of 2500 x 290 m resembling the Lower Triassic aquifer of the Paris basin, consisting of 2 layers of sandstone separated by a layer of conglomerates. The domain dips 0.5% from east to west. The top of the aquifer is 500 m-deep and the lateral boundaries are assumed to be open. This case is considered conservative compared to a dome-like geological trap, which could be more favorable to retain higher gas concentration. A number of cycles of gas production and injection were modelled. An automatic shut-down of the pump is implemented in case pressure on the well exceeds an upper or lower threshold. The influence of the position of the well, the uncertain residual gas saturation and the regional flow are studied. The model shows that both gas and aquifer properties have a significant impact on storage. Due to its low viscosity, the mobility of the hythane is quite high and gas expands significantly, reducing

  3. Safety issues of dry fuel storage at RSWF

    International Nuclear Information System (INIS)

    Clarksean, R.L.; Zahn, T.P.

    1995-01-01

    Safety issues associated with the dry storage of EBR-II spent fuel are presented and discussed. The containers for the fuel have been designed to prevent a leak of fission gases to the environment. The storage system has four barriers for the fission gases. These barriers are the fuel cladding, an inner container, an outer container, and the liner at the RSWF. Analysis has shown that the probability of a leak to the environment is much less than 10 -6 per year, indicating that such an event is not considered credible. A drop accident, excessive thermal loads, criticality, and possible failure modes of the containers are also addressed

  4. Dry storage developments in France build on CASCAD experience

    International Nuclear Information System (INIS)

    Bonnet, C.; Giraud, C.

    1992-01-01

    The CASCAD dry store, located at CEA's research centre at Cadarache, stores spent fuel from the EL4 heavy water reactor and the Osiris research reactor. The design was based on the following criteria: Storage period. Interim storage is provided for 50 years. Containment. The fuel is contained by a multiple barrier system consisting of: the fuel canister (primary barrier); the sealed stainless steel storage well; and the storage building which includes a ventilation system to provide dynamic containment during handling operations. The fuel is loaded into canisters at the reactor site to avoid contamination in the storage building. The integrity of the primary barrier is periodically monitored by sampling of air from the storage well. Cooling. The storage wells are cooled by a natural convection system that maintains the temperature of the fuel below its stated limit and the temperature of the concrete below 80 o C. Criticality. Criticality incidents are prevented by static design measures such as maintaining a minimum pitch between storage wells and providing sufficient storage well diameter. Radiation protection. Radiation shielding limits the maximum equivalent dose rate for operating personnel to less than 25μSv/h at the handling cell floor and the wall adjoining the control room, and to less than 7.5μSv/h at the outside walls of the storage building. Cannister design. The canister must resist corrosion caused by condensation as well as pressure due to radiolytic gases. The canister must also withstand a drop of up to 10m without losing its integrity. The design has now been adapted to accommodate light reactor fuels and is known as CASCAD+. (Author)

  5. Corrosion of aluminum alloys in simulated dry storage environments

    International Nuclear Information System (INIS)

    Peacock, H.B. Jr.; Sindelar, R.L.; Lam, P.S.

    1996-01-01

    The effect of temperature and relative humidity on the high temperature (up to 150 degrees C) corrosion of aluminum alloys was investigated for dry storage of spent nuclear fuels in a closed or sealed system. A dependency on alloy type, temperature and initial humidity was determined for 1100, 5052 and 6061 aluminum alloys. Results after 4500 hours of environmental testing show that for a closed system, corrosion tends to follow a power law with the rate decreasing with increasing exposure. As corrosion takes place, two phenomena occur: (1) a hydrated layer builds up to resist corrosion, and (2) moisture is depleted from the system and the humidity slowly decreases with time. At a critical level of relative humidity, corrosion reactions stop, and no additional corrosion occurs if the system remains closed. The results form the basis for the development of an acceptance criteria for the dry storage of aluminum clad spent nuclear fuels

  6. Multiple-Angle Muon Radiography of a Dry Storage Cask

    Energy Technology Data Exchange (ETDEWEB)

    Durham, J. Matthew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Guardincerri, Elena [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Morris, Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Poulson, Daniel Cris [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Bacon, Jeffrey Darnell [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Morley, Deborah Jean [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Plaud-Ramos, Kenie Omar [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-01-23

    A partially loaded dry storage cask was imaged using cosmic ray muons. Since the cask is large relative to the size of the muon tracking detectors, the instruments were placed at nine different positions around the cask to record data covering the entire fuel basket. We show that this technique can detect the removal of a single fuel assembly from the center of the cask.

  7. Protocols for dry DNA storage and shipment at room temperature.

    Science.gov (United States)

    Ivanova, Natalia V; Kuzmina, Masha L

    2013-09-01

    The globalization of DNA barcoding will require core analytical facilities to develop cost-effective, efficient protocols for the shipment and archival storage of DNA extracts and PCR products. We evaluated three dry-state DNA stabilization systems: commercial Biomatrica(®) DNAstable(®) plates, home-made trehalose and polyvinyl alcohol (PVA) plates on 96-well panels of insect DNA stored at 56 °C and at room temperature. Controls included unprotected samples that were stored dry at room temperature and at 56 °C, and diluted samples held at 4 °C and at -20 °C. PCR and selective sequencing were performed over a 4-year interval to test the condition of DNA extracts. Biomatrica(®) provided better protection of DNA at 56 °C and at room temperature than trehalose and PVA, especially for diluted samples. PVA was the second best protectant after Biomatrica(®) at room temperature, whereas trehalose was the second best protectant at 56 °C. In spite of lower PCR success, the DNA stored at -20 °C yielded longer sequence reads and stronger signal, indicating that temperature is a crucial factor for DNA quality which has to be considered especially for long-term storage. Although it is premature to advocate a transition to DNA storage at room temperature, dry storage provides an additional layer of security for frozen samples, protecting them from degradation in the event of freezer failure. All three forms of DNA preservation enable shipment of dry DNA and PCR products between barcoding facilities. © 2013 The Authors. Molecular Ecology Resources published by John Wiley & Sons Ltd.

  8. Interim dry storage system technologies and innovations VARNA 2002

    International Nuclear Information System (INIS)

    Chollet, P.; Guenon, Y.

    2002-01-01

    The main concepts of the TN24 Family and NUHOMS System are explained in the paper. It is discussed how the NPPs specific requirements and economics trends contributes to the growing families of interim dry storage systems delivered under COGEMA LOGICTICS license. It is concluded that modular solutions are currently dominating because they are derived from main concepts evolved over time, benefited from both the transport aspects with internationally recognised stringent regulations, and various specific ISFSI requirements and economic trends

  9. Challenges to and proposals for underground gas storage (UGS business in China

    Directory of Open Access Journals (Sweden)

    Gangxiong Zhang

    2017-05-01

    Full Text Available Underground gas storage (UGS is one of the major storage and peak-shaving means in the world among numerous storage ways via gas fields, small-scale LNG, etc. With the rapid development of natural gas industry in China, the seasonal peak-shaving issues are increasingly prominent, so how to achieve sustainable development of UGS business has become a major problem at present. In view of this, we studied the present status and trend of UGS development abroad and analyzed the following challenges encountered by UGS in China. (1 UGS construction falls behind the world and peak-shaving capacity is insufficient. (2 There is lack of quality gas sources for storage and the complicated geological conditions make the cost of UGS construction high. (3 UGS construction is still at the preliminary stage, so experience is not enough in safety and scientific operation and management. (4 UGS construction, management and operation are not unified as a whole, so its maximum efficiency fails to be exerted. (5 The economic benefit of UGS is difficult to be shown without independent cost accounting. Based on the experience of other countries, some proposals were put forward on UGS development under the actual present situation: to strengthen strategic UGS layout, intensify storage site screening in key areas and steadily promote UGS construction; to establish professional UGS technical and management teams and intensify the research of key technologies; and to set up a complete and rationally-distributed UGS construction, operation and management system.

  10. 3rd Sino-German Conference “Underground Storage of CO2 and Energy”

    CERN Document Server

    Xie, Heping; Were, Patrick

    2013-01-01

    Anthropogenic greenhouse gas emissions, energy security and sustainability are three of the greatest contemporary global challenges today. This year the Sino-German Cooperation Group “Underground Storage of CO2 and Energy”, is meeting on the 21-23 May 2013 for the second time in Goslar, Germany, to convene its 3rd Sino-German conference on the theme “Clean Energy Systems in the Subsurface: Production, Storage and Conversion”.   This volume is a collection of diverse quality scientific works from different perspectives elucidating on the current developments in CO2 geologic sequestration research to reduce greenhouse emissions including measures to monitor surface leakage, groundwater quality and the integrity of caprock, while ensuring a sufficient supply of clean energy. The contributions herein have been structured into 6 major thematic research themes: Integrated Energy and Environmental Utilization of Geo-reservoirs: Law, Risk Management & Monitoring CO2 for Enhanced Gas and Oil Recovery, Coa...

  11. On thermal properties of hard rocks as a host environment of an underground thermal energy storage

    Science.gov (United States)

    Novakova, L.; Hladky, R.; Broz, M.; Novak, P.; Lachman, V.; Sosna, K.; Zaruba, J.; Metelkova, Z.; Najser, J.

    2013-12-01

    With increasing focus on environmentally friendly technologies waste heat recycling became an important issue. Under certain circumstances subsurface environment could be utilized to accommodate relatively large quantity of heat. Industrial waste heat produced during warm months can be stored in an underground thermal energy storage (UTES) and used when needed. It is however a complex task to set up a sustainable UTES for industrial scale. Number of parameters has to be studied and evaluated by means of thermohydromechanical and chemical coupling (THMC) before any UTES construction. Thermal characteristics of various rocks and its stability under thermal loading are amongst the most essential. In the Czech Republic study two complementary projects THMC processes during an UTES operation. The RESEN project (www.resen.cz) employs laboratory tests and experiments to characterise thermal properties of hard rocks in the Bohemian Massif. Aim of the project is to point out the most suitable rock environment in the Bohemian Massif for moderate to ultra-high temperature UTES construction (Sanyal, 2005). The VITA project (www.geology.cz/mokrsko) studies THM coupling in non-electrical temperature UTES using long term in-situ experiment. In both projects thermal properties of rocks were studied. Thermal conductivity and capacity were measured on rock samples. In addition an influence of increasing temperature and moisture content was considered. Ten hard rocks were investigated. The set included two sandstones, two ignibrites, a melaphyr, a syenite, two granites, a gneiss and a serpentinite. For each rock there were measured thermal conductivity and capacity of at least 54 dried samples. Subsequently, the samples were heated up to 380°C in 8 hours and left to cool down. Thermal characteristics were measured during the heating period and after the sample reached room temperature. Heating and cooling cycle was repeated 7 to 10 times to evaluate possible UTES-like degradation of

  12. Relevance of deep-subsurface microbiology for underground gas storage and geothermal energy production.

    Science.gov (United States)

    Gniese, Claudia; Bombach, Petra; Rakoczy, Jana; Hoth, Nils; Schlömann, Michael; Richnow, Hans-Hermann; Krüger, Martin

    2014-01-01

    This chapter gives the reader an introduction into the microbiology of deep geological systems with a special focus on potential geobiotechnological applications and respective risk assessments. It has been known for decades that microbial activity is responsible for the degradation or conversion of hydrocarbons in oil, gas, and coal reservoirs. These processes occur in the absence of oxygen, a typical characteristic of such deep ecosystems. The understanding of the responsible microbial processes and their environmental regulation is not only of great scientific interest. It also has substantial economic and social relevance, inasmuch as these processes directly or indirectly affect the quantity and quality of the stored oil or gas. As outlined in the following chapter, in addition to the conventional hydrocarbons, new interest in such deep subsurface systems is rising for different technological developments. These are introduced together with related geomicrobiological topics. The capture and long-termed storage of large amounts of carbon dioxide, carbon capture and storage (CCS), for example, in depleted oil and gas reservoirs, is considered to be an important options to mitigate greenhouse gas emissions and global warming. On the other hand, the increasing contribution of energy from natural and renewable sources, such as wind, solar, geothermal energy, or biogas production leads to an increasing interest in underground storage of renewable energies. Energy carriers, that is, biogas, methane, or hydrogen, are often produced in a nonconstant manner and renewable energy may be produced at some distance from the place where it is needed. Therefore, storing the energy after its conversion to methane or hydrogen in porous reservoirs or salt caverns is extensively discussed. All these developments create new research fields and challenges for microbiologists and geobiotechnologists. As a basis for respective future work, we introduce the three major topics, that is

  13. Management of dry flue gas desulfurization by-products in underground mines. Annual report, October 1994--September 1995

    Energy Technology Data Exchange (ETDEWEB)

    Chugh, Y.P.; Dutta, D.; Esling, S. [and others

    1995-10-01

    On September 30, 1993, the U.S. Department of Energy-Morgantown Energy Technology Center (DOE-METC) and Southern Illinois University at Carbondale (SIUC) entered into a cooperative research agreement entitled {open_quotes}Management of Dry Flue Gas Desulfurization By-Products in Underground Mines{close_quotes} (DE-FC21-93MC30252). Under the agreement Southern Illinois University at Carbondale will develop and demonstrate several technologies for the placement of coal combustion residues (CCBs) in abandoned coal mines, and will assess the environmental impact of such underground CCB placement. This report describes progress in the following areas: environmental characterization, mix development and geotechnical characterization, material handling and system economics, underground placement, and field demonstration.

  14. An Assessment of Hydrological Safety for the Guri Underground Oil Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Geon Young; Kim, Kyung Su; Koh, Yong Kwon; Bae, Dae Seok; Park, Kyung Woo; Ji, Sung Hoon; Ryu, Ji Hoon

    2009-08-15

    Hydrological and geochemical analysis of the various kinds of water including observation borehole groundwater was carried out for the assessment of the hydrological safety of the underground oil storage cavern and the potentiality of mineralogical and microbiological clogging was estimated. There was no distinct chemical difference in the various kinds of water. All kinds of water are undersaturated with the calcite which is the major clogging mineral. Most water samples have low Fe and Mn concentrations. However, they are saturated or oversaturated with the iron-oxide/hydroxide minerals and have high dissolved oxygen contents which softiies the possibility of clogging by the iron-oxide/hydroxide minerals as a long-term aspect. Statistical analysis shows the degree of mineral precipitation or dissolution is mainly controlled by pH, Eh and DO of water samples. Because the slime forming bacteria ate dominant microbe in several observation boreholes, the clogging can be caused by it as a long-term aspect. In addition, the possibility of clogging can be increased if the microbial effect is combined with the mineralogical effect such as iron oxide/hydroxide minerals for the possibility of clogging. Therefore, the systematic and long-term program for the assessment of clogging is required for the safe operation of underground oil storage cavern.

  15. An Assessment of Hydrological Safety for the Guri Underground Oil Storage Facility

    International Nuclear Information System (INIS)

    Kim, Geon Young; Kim, Kyung Su; Koh, Yong Kwon; Bae, Dae Seok; Park, Kyung Woo; Ji, Sung Hoon; Ryu, Ji Hoon

    2009-08-01

    Hydrological and geochemical analysis of the various kinds of water including observation borehole groundwater was carried out for the assessment of the hydrological safety of the underground oil storage cavern and the potentiality of mineralogical and microbiological clogging was estimated. There was no distinct chemical difference in the various kinds of water. All kinds of water are undersaturated with the calcite which is the major clogging mineral. Most water samples have low Fe and Mn concentrations. However, they are saturated or oversaturated with the iron-oxide/hydroxide minerals and have high dissolved oxygen contents which softiies the possibility of clogging by the iron-oxide/hydroxide minerals as a long-term aspect. Statistical analysis shows the degree of mineral precipitation or dissolution is mainly controlled by pH, Eh and DO of water samples. Because the slime forming bacteria ate dominant microbe in several observation boreholes, the clogging can be caused by it as a long-term aspect. In addition, the possibility of clogging can be increased if the microbial effect is combined with the mineralogical effect such as iron oxide/hydroxide minerals for the possibility of clogging. Therefore, the systematic and long-term program for the assessment of clogging is required for the safe operation of underground oil storage cavern

  16. DOE underground storage tank waste remediation chemical processing hazards. Part I: Technology dictionary

    International Nuclear Information System (INIS)

    DeMuth, S.F.

    1996-10-01

    This document has been prepared to aid in the development of Regulating guidelines for the Privatization of Hanford underground storage tank waste remediation. The document has been prepared it two parts to facilitate their preparation. Part II is the primary focus of this effort in that it describes the technical basis for established and potential chemical processing hazards associated with Underground Storage Tank (UST) nuclear waste remediation across the DOE complex. The established hazards involve those at Sites for which Safety Analysis Reviews (SARs) have already been prepared. Potential hazards are those involving technologies currently being developed for future applications. Part I of this document outlines the scope of Part II by briefly describing the established and potential technologies. In addition to providing the scope, Part I can be used as a technical introduction and bibliography for Regulatory personnel new to the UST waste remediation, and in particular Privatization effort. Part II of this document is not intended to provide examples of a SAR Hazards Analysis, but rather provide an intelligence gathering source for Regulatory personnel who must eventually evaluate the Privatization SAR Hazards Analysis

  17. Tools for Inspecting and Sampling Waste in Underground Radioactive Storage Tanks with Small Access Riser Openings

    International Nuclear Information System (INIS)

    Nance, T.A.

    1998-01-01

    Underground storage tanks with 2 inches to 3 inches diameter access ports at the Department of Energy's Savannah River Site have been used to store radioactive solvents and sludge. In order to close these tanks, the contents of the tanks need to first be quantified in terms of volume and chemical and radioactive characteristics. To provide information on the volume of waste contained within the tanks, a small remote inspection system was needed. This inspection system was designed to provide lighting and provide pan and tilt capabilities in an inexpensive package with zoom abilities and color video. This system also needed to be utilized inside of a plastic tent built over the access port to contain any contamination exiting from the port. This system had to be build to travel into the small port opening, through the riser pipe, into the tank evacuated space, and out of the riser pipe and access port with no possibility of being caught and blocking the access riser. Long thin plates were found in many access riser pipes that blocked the inspection system from penetrating into the tank interiors. Retrieval tools to clear the plates from the tanks using developed sampling devices while providing safe containment for the samples. This paper will discuss the inspection systems, tools for clearing access pipes, and solvent sampling tools developed to evaluate the tank contents of the underground solvent storage tanks

  18. Method of disposing of earth contaminated by leaking underground storage tanks

    International Nuclear Information System (INIS)

    Ruehl, P.A.

    1993-01-01

    A process is described for disposing of earth contaminated with petroleum products from a leaking underground storage tank wherein the earth contains a significant amount of material comprised primarily of a mixture of one part Al 2 O 3 and two to three parts SiO 2 , the process comprising: digging up a leaking underground storage tank and the surrounding contaminated earth; separating the excavated earth into a Al 2 O 3 +SiO 2 material and a non-Al 2 O 3 + SiO 2 material; mixing the Al 2 O 3 + SiO 2 material and other cement precursor raw materials together to form a mixture, and grinding the mixture to form a feed mix; introducing the feed mix into a rotary cement kiln causing any remaining petroleum product contained therein to be volatilized and burned within the kiln as cement clinker is being produced; and grinding the cement clinker together to form cement which is free of petroleum product

  19. Feasibility studies for pump and treat technology at leaking underground storage tank sites in Michigan

    International Nuclear Information System (INIS)

    O'Brien, J.M.; Pekas, B.S.

    1993-01-01

    Releases from underground storage tanks have resulted in impacts to groundwater at thousands of sites across the US. Investigations of these sites were initiated on a national basis with the implementation of federal laws that became effective December 22, 1989 (40 CFR 280). Completion of these investigations has led to a wave of design and installation of pump and treat aquifer restoration systems where impacts to groundwater have been confirmed. The purpose of this paper is to provide managers with a demonstration of some of the techniques that can be used by the consulting industry in evaluating the feasibility of pump and treat systems. With knowledge of these tools, managers can better evaluate proposals for system design and their cost effectiveness. To evaluate the effectiveness of typical pump and treat systems for leaking underground storage tank (LUST) sites in Michigan, ten sites where remedial design had been completed were randomly chosen for review. From these ten, two sites were selected that represented the greatest contrast in the types of site conditions encountered. A release of gasoline at Site 1 resulted in contamination of groundwater and soil with benzene, toluene, ethylbenzene, and xylenes

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

    International Nuclear Information System (INIS)

    1981-11-01

    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

  1. FRAPCON analysis of cladding performance during dry storage operations

    Energy Technology Data Exchange (ETDEWEB)

    Richmond, David J.; Geelhood, Kenneth J.

    2018-03-01

    There is an increasing need in the U.S. and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations (ISFSI) or interim storage sites. The NRC limits cladding temperature to 400°C while maintaining cladding hoop stress below 90 MPa in an effort to avoid radial hydride reorientation. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at 400 °C. Results were representative of the majority of U.S. LWR fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage.

  2. Survey of experience with dry storage of spent nuclear fuel and update of wet storage experience

    International Nuclear Information System (INIS)

    1988-01-01

    Spent fuel storage is an important part of spent fuel management. At present about 45,000 t of spent water reactor fuel have been discharged worldwide. Only a small fraction of this fuel (approximately 7%) has been reprocessed. The amount of spent fuel arisings will increase significantly in the next 15 years. Estimates indicate that up to the year 2000 about 200,000 t HM of spent fuel could be accumulated. In view of the large quantities of spent fuel discharged from nuclear power plants and future expected discharges, many countries are involved in the construction of facilities for the storage of spent fuel and in the development of effective methods for spent fuel surveillance and monitoring to ensure that reliable and safe operation of storage facilities is achievable until the time when the final disposal of spent fuel or high level wastes is feasible. The first demonstrations of final disposal are not expected before the years 2000-2020. This is why the long term storage of spent fuel and HLW is a vital problem for all countries with nuclear power programmes. The present survey contains data on dry storage and recent information on wet storage, transportation, rod consolidation, etc. The main aim is to provide spent fuel management policy making organizations, designers, scientists and spent fuel storage facility operators with the latest information on spent fuel storage technology under dry and wet conditions and on innovations in this field. Refs, figs and tabs

  3. Current status of ground source heat pumps and underground thermal energy storage in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Sanner, B. [Justus Liebig University, Giessen (Germany). Institute of Applied Geosciences; Karytsas, C.; Mendrinos, D. [Center for Renewable Energy Sources, Pikermi (Greece); Rybach, L. [Geowatt AG, Zurich (Switzerland)

    2003-12-01

    Geothermal Heat Pumps, or Ground Coupled Heat Pumps (GCHP), are systems combining a heat pump with a ground heat exchanger (closed loop systems), or fed by ground water from a well (open loop systems). They use the earth as a heat source when operating in heating mode, with a fluid (usually water or a water-antifreeze mixture) as the medium that transfers the heat from the earth to the evaporator of the heat pump, thus utilising geothermal energy. In cooling mode, they use the earth as a heat sink. With Borehole Heat Exchangers (BHE), geothermal heat pumps can offer both heating and cooling at virtually any location, with great flexibility to meet any demands. More than 20 years of R and D focusing on BUE in Europe has resulted in a well-established concept of sustainability for this technology, as well as sound design and installation criteria. Recent developments are the Thermal Response Test, which allows in-situ-determination of ground thermal properties for design purposes, and thermally enhanced grouting materials to reduce borehole thermal resistance. For cooling purposes, but also for the storage of solar or waste heat, the concept of underground thermal energy storage (UTES) could prove successful. Systems can be either open (aquifer storage) or can use BHE (borehole storage). Whereas cold storage is already established on the market, heat storage, and, in particular, high temperature heat storage (> 50{sup o}C) is still in the demonstration phase. Despite the fact that geothermal heat pumps have been in use for over 50 years now (the first were in the USA), market penetration of this technology is still in its infancy, with fossil fuels dominating the space heating market and air-to-air heat pumps that of space cooling. In Germany, Switzerland, Austria, Sweden, Denmark, Norway, France and the USA, large numbers of geothermal heat pumps are already operational, and installation guidelines, quality control and contractor certification are now major issues

  4. Survey of wet and dry spent fuel storage

    International Nuclear Information System (INIS)

    1999-07-01

    Spent fuel storage is one of the important stages in the nuclear fuel cycle and stands among the most vital challenges for countries operating nuclear power plants. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and for coordinating and encouraging closer co-operation among Member States. Spent fuel management is recognized as a high priority IAEA activity. In 1997, the annual spent fuel arising from all types of power reactors worldwide amounted to about 10,500 tonnes heavy metal (t HM). The total amount of spent fuel accumulated worldwide at the end of 1997 was about 200,000 t HM of which about 130,000 t HM of spent fuel is presently being stored in at-reactor (AR) or away-from-reactor (AFR) storage facilities awaiting either reprocessing or final disposal and 70,000 t HM has been reprocessed. Projections indicate that the cumulative amount generated by 2010 may surpass 340,000 t HM and by the year 2015 395,000 t HM. Part of the spent fuel will be reprocessed and some countries took the option to dispose their spent fuel in a repository. Most countries with nuclear programmes are using the deferral of a decision approach, a 'wait and see' strategy with interim storage, which provides the ability to monitor the storage continuously and to retrieve the spent fuel later for either direct disposal or reprocessing. Some countries use different approaches for different types of fuel. Today the worldwide reprocessing capacity is only a fraction of the total spent fuel arising and since no final repository has yet been constructed, there will be an increasing demand for interim storage. The present survey contains information on the basic storage technologies and facility types, experience with wet and dry storage of spent fuel and international experience in spent fuel transport. The main aim is to provide spent fuel

  5. 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.

  6. 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.

  7. A GIS Based 3D Online Decision Assistance System for Underground Energy Storage in Northern Germany

    Science.gov (United States)

    Nolde, M.; Schwanebeck, M.; Biniyaz, E.; Duttmann, R.

    2014-12-01

    We would like to present a GIS-based 3D online decision assistance system for underground energy storage. Its aim is to support the local land use planning authorities through pre-selection of possible sites for thermal, electrical and substantial underground energy storages. Since the extension of renewable energies has become legal requirement in Germany, the underground storing of superfluously produced green energy (such as during a heavy wind event) in the form of compressed air, gas or heated water has become increasingly important. However, the selection of suitable sites is a complex task. The assistance system uses data of geological features such as rock layers, salt caverns and faults enriched with attribute data such as rock porosity and permeability. This information is combined with surface data of the existing energy infrastructure, such as locations of wind and biogas stations, power line arrangement and cable capacity, and energy distribution stations. Furthermore, legal obligations such as protected areas on the surface and current underground mining permissions are used for the decision finding process. Not only the current situation but also prospective scenarios, such as expected growth in produced amount of energy are incorporated in the system. The decision process is carried out via the 'Analytic Hierarchy Process' (AHP) methodology of the 'Multi Object Decision Making' (MODM) approach. While the process itself is completely automated, the user has full control of the weighting of the different factors via the web interface. The system is implemented as an online 3D server GIS environment, with no software needed to be installed on the user side. The results are visualized as interactive 3d graphics. The implementation of the assistance system is based exclusively on free and open source software, and utilizes the 'Python' programming language in combination with current web technologies, such as 'HTML5', 'CSS3' and 'JavaScript'. It is

  8. Panorama 2014 - The importance of underground storage in the security of European gas supplies

    International Nuclear Information System (INIS)

    Cornot-Gandolphe, Sylvie

    2013-12-01

    While European capacity for underground gas storage has increased by 16% over the last three years, levels of stock at the beginning of the 2013/2014 winter, in relation to capacity, are the lowest that have been seen since 2010; they represent only 84% of storage capacity. The suppliers of gas have no incentive to reserve storage capacity, for which the cost is considered too high in relation to the spread, currently very low, between the price of gas in winter and in summer. They also rely on sufficient gas supply thanks to other sources of flexibility available on the market: flexibility of production or imports, spot LNG purchases, purchases in the spot market... or even use of the storage capacities of neighbouring countries via European network interconnections. Yet, the 2013/2014 winter is beginning in a gas supply context in Europe that is more difficult: imports of LNG, which had already dropped sharply in 2012, have continued to contract, faced with increased competition from Asian buyers on the international LNG market. Gas imports from Norway are also declining following production limits in that country. Only Russia has strongly increased its exports to Europe in 2013. However, the dispute between Ukraine and Russia about the price of Russian gas delivered to Ukraine still raises the spectre of a threat to the European supply of Russian gas, nearly 60% of which transits via Ukraine. Under these circumstances, as demonstrated by the gas crises of 2006 and 2009 and the cold conditions of February 2012 and March/April 2013, storage is the most efficient means of securing the supply of gas providing, of course, that the storage sites are filled at the beginning of winter. (author)

  9. SGN multipurpose dry storage technology applied to the Italian situation

    International Nuclear Information System (INIS)

    Giorgio, M.; Lanza, R.

    1999-01-01

    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 multipurpose facilities capable of accommodating all types of waste in a single structure. The pooling of certain functions (transport cask reception, radiation protection) and the choice of optimized technologies to answer the specific needs of clients (transfer of nuclear packages by shielded handling cask or nuclearized crane), the use of the same type of storage pit to cool the heat releasing packages (vitrified nuclear waste, fuel elements) makes it possible to propose industrially proven and cost-effective solutions. Studies carried out for the Dutch company COVRA (HABOG facility currently under implementation phase) provide an example of a multipurpose dry storage facility designed to store spent fuel, vitrified reprocessing waste, cemented hulls and end-pieces, cemented technological waste and bituminized waste from fuel reprocessing, i e. high level waste and intermediate level wastes. The study conducted by SGN and GENESI (an Italian consortium formed by Ansaldo's Nuclear Division and Fiat Avio), on behalf of the Italian utility ENEL, offers another example of the multipurpose dry storage facility designed to store in a centralised site all the remaining irradiated fuel elements plus the vitrified waste. This paper presents SGN's experience through a short description of reference storage facilities for various types of products (HLW and spent fuel). It continues with the typical application to the Italian situation to show how these proven technologies are combined to obtain multipurpose facilities tailored to the client's specific requirements. (author)

  10. Licensing of spent nuclear fuel dry storage in Russia

    International Nuclear Information System (INIS)

    Kislov, A.I.; Kolesnikov, A.S.

    1999-01-01

    The Federal nuclear and radiation safety authority of Russia (Gosatomnadzor) being the state regulation body, organizes and carries out the state regulation and supervision for safety at handling, transport and storage of spent nuclear fuel. In Russia, the use of dry storage in casks will be the primary spent nuclear fuel storage option for the next twenty years. The cask for spent nuclear fuel must be applied for licensing by Gosatomnadzor for both storage and transportation. There are a number of regulations for transportation and storage of spent nuclear fuel in Russia. Up to now, there are no special regulations for dry storage of spent nuclear fuel. Such regulations will be prepared up to the end of 1998. Principally, it will be required that only type B(U)F, packages can be used for interim storage of spent nuclear fuel. Recently, there are two dual-purpose cask designs under consideration in Russia. One of them is the CONSTOR steel concrete cask, developed in Russia (NPO CKTI) under the leadership of GNB, Germany. The other cask design is the TUK-104 cask of KBSM, Russia. Both cask types were designed for spent nuclear RBMK fuel. The CONSTOR steel concrete cask was designed to be in full compliance with both Russian and IAEA regulations for transport of packages for radioactive material. The evaluation of the design criteria by Russian experts for the CONSTOR steel concrete cask project was performed at a first stage of licensing (1995 - 1997). The CONSTOR cask design has been assessed (strength analysis, thermal physics, nuclear physics and others) by different Russian experts. To show finally the compliance of the CONSTOR steel concrete cask with Russian and IAEA regulations, six drop tests have been performed with a 1:2 scale model manufactured in Russia. A test report was prepared. The test results have shown that the CONSTOR cask integrity is guaranteed under both transport and storage accident conditions. The final stage of the certification procedure

  11. Dry interim storage of radioactive material in Germany

    International Nuclear Information System (INIS)

    Drobniewski, Christian; Palmes, Julia

    2013-01-01

    In accordance with the waste management concept in Germany, spent fuel is stored in interim storage facilities for a period of up to 40 years until deposition in a geological repository. In twelve on-site interim storages in the vicinity or directly on the sites of the nuclear power plants, spent fuel elements from reactor operation are stored after the necessary period of decay in wet storage basins inside the reactors. Additionally, three central interim storage facilities for storage of spent fuel of different origin are in operation. The German facilities realize the concept of dry interim storage in metallic transport and storage casks. The confinement of the radioactive material is ensured by the double lid system of the casks, of which the leak tightness is monitored constantly. The casks are constructed to provide adequate heat removal and shielding of gamma and neutron radiation. Usually the storage facilities are halls of thick concrete structures, which ensure the removal of the decay heat by natural convection. The main safety goal of the storage concept is to prevent unnecessary exposure of persons, material goods and environment to ionizing radiation. Moreover any exposure should be kept as low as reasonable achievable. To reach this goal the containment of the radioactive materials, the disposal of decay heat, the sub criticality and the shielding of ionizing radiation has to be demonstrated by the applicant and verified by the licensing authority. In particular accidents, incidents and disasters have to be considered in the facility and cask design. This includes mechanical impacts onto the cask, internal and external fire, and environmental effects like wind, rain, snowfall, flood, earthquakes and landslides. In addition civilizatoric influences like plane crashes and explosions have to be taken into account. In all mentioned cases the secure confinement of the radioactive materials has to be ensured. On-site storage facilities have to consider the

  12. Scientific basis for storage criteria for interim dry storage of aluminum-clad fuels

    International Nuclear Information System (INIS)

    Sindelar, R.L.; Peacock, H.B. Jr.; Lam, P.S.; Iyer, N.C.; Louthan, M.R. Jr.; Murphy, J.R.

    1996-01-01

    An engineered system for dry storage of aluminum-clad foreign and domestic research reactor spent fuel owned by the US Department of Energy is being considered to store the fuel up to a nominal period of 40 years prior to ultimate disposition. Scientifically-based criteria for environmental limits to drying and storing the fuels for this system are being developed to avoid excessive degradation in sealed and non-sealed (open to air) dry storage systems. These limits are based on consideration of degradation modes that can cause loss of net section of the cladding, embrittlement of the cladding, distortion of the fuel, or release of fuel and fission products from the fuel/clad system. Potential degradation mechanisms include corrosion mechanisms from exposure to air and/or sources of humidity, hydrogen blistering of the aluminum cladding, distortion of the fuel due to creep, and interdiffusion of the fuel and fission products with the cladding. The aluminum-clad research reactor fuels are predominantly highly-enriched aluminum uranium alloy fuel which is clad with aluminum alloys similar to 1100, 5052, and 6061 aluminum. In the absence of corrodant species, degradation due to creep and diffusion mechanisms limit the maximum fuel storage temperature to 200 C. The results of laboratory scale corrosion tests indicate that this fuel could be stored under air up to 200 C at low relative humidity levels (< 20%) to limit corrosion of the cladding and fuel (exposed to the storage environment through assumed pre-existing pits in the cladding). Excessive degradation of fuels with uranium metal up to 200 C can be avoided if the fuel is sufficiently dried and contained in a sealed system; open storage can be achieved if the temperature is controlled to avoid excessive corrosion even in dry air

  13. Development of the vacuum drying process for the PWR spent nuclear fuel dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Baeg, Chagn Yeal; Cho, Chun Hyung [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-12-15

    This paper describes the development of a dry operation process for PWR spent nuclear fuel, which is currently stored in the domestic NPP's storage pool, using a dual purpose metal cask. Domestic NNPs have had experience with wet type transportation of PWR spent nuclear fuel between neighboring NPPs since the early 1990s, but no experience with dry type operation. For this reason, we developed a specific operation process and also confirmed the safety of the major cask components and its spent nuclear fuel during the dual purpose metal cask operation process. We also describe the short term operation process that was established to be completed within 21 hours and propose the allowable working time for each step (15 hours for wet process, 3 hours for drain process and 3 hours for vacuum drying process)

  14. Geochemistry research planning for the underground storage of high-level nuclear waste

    International Nuclear Information System (INIS)

    Apps, J.A.

    1983-09-01

    This report is a preliminary attempt to plan a comprehensive program of geochemistry research aimed at resolving problems connected with the underground storage of high-level nuclear waste. The problems and research needs were identified in a companion report to this one. The research needs were taken as a point of departure and developed into a series of proposed projects with estimated manpowers and durations. The scope of the proposed research is based on consideration of an underground repository as a multiple barrier system. However, the program logic and organization reflect conventional strategies for resolving technological problems. The projects were scheduled and the duration of the program, critical path projects and distribution of manpower determined for both full and minimal programs. The proposed research was then compared with ongoing research within DOE, NRC and elsewhere to identify omissions in current research. Various options were considered for altering the scope of the program, and hence its cost and effectiveness. Finally, recommendations were made for dealing with omissions and uncertainties arising from program implementation. 11 references, 6 figures, 4 tables

  15. Dry storage of spent nuclear fuel: present principles

    International Nuclear Information System (INIS)

    Vapirev, E.; Christoskov, I.; Boyadjiev, Z.

    1998-01-01

    The basic principles for the dry storage of spent nuclear fuel are presented in accordance to the author's understanding. The are: 1) Storage in the air at a low temperature (below 200 o C) or in a inert atmosphere (nitrogen, helium) at a temperature up to 300-400 o C; 2) Passive cooling by air; 3) Multiple barriers to the propagation of fission products and trans-uraniums: fuel palette, fuel pin cladding, a containment or a canister, a single or a double cover of the container; 4) Control of the condition of the atmosphere within the double cover - pressure monitoring, helium concentration monitoring (if the atmosphere in the container is of helium or contains traces of helium). Based on publications, observations and discussion during the recent years, several principles are propose for discussion. It is proposed: 4) Stored fuel must be regarded as defective; 5) Active control of the integrity of the protective barriers of of the composition of the storage atmosphere - principle of the 'control barrier' or the 'control atmosphere'; 6) Introduction of the procedure of 'check up of the condition of SNF' by visual control or sampling of the storage atmosphere for the technologies which do not provide for monitoring the integrity of barriers or of the storage atmosphere. Principle 4 is being gradually accepted in modern technologies. Principle 5 is observed in the double-purpose containers and in some of MVDS technologies. A common feature of the technologies of horizontal and vertical canister storage in concrete modules is the absence of control of the integrity of barriers or of the composition of the atmosphere. To these technologies, if they are not revised, principle 6 applies

  16. Review of sensors for the in situ chemical characterization of the Hanford underground storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Kyle, K.R.; Mayes, E.L.

    1994-07-29

    Lawrence Livermore National Laboratory (LLNL), in the Technical Task Plan (TTP) SF-2112-03 subtask 2, is responsible for the conceptual design of a Raman probe for inclusion in the in-tank cone penetrometer. As part of this task, LLNL is assigned the further responsibility of generating a report describing a review of sensor technologies other than Raman that can be incorporated in the in-tank cone penetrometer for the chemical analysis of the tank environment. These sensors would complement the capabilities of the Raman probe, and would give information on gaseous, liquid, and solid state species that are insensitive to Raman interrogation. This work is part of a joint effort involving several DOE laboratories for the design and development of in-tank cone penetrometer deployable systems for direct UST waste characterization at Westinghouse Hanford Company (WHC) under the auspices of the U.S. Department of Energy (DOE) Underground Storage Tank Integrated Demonstration (UST-ID).

  17. Corrective action baseline report for underground storage tank 2331-U Building 9201-1

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this report is to provide baseline geochemical and hydrogeologic data relative to corrective action for underground storage tank (UST) 2331-U at the Building 9201-1 Site. Progress in support of the Building 9201-1 Site has included monitoring well installation and baseline groundwater sampling and analysis. This document represents the baseline report for corrective action at the Building 9201-1 site and is organized into three sections. Section 1 presents introductory information relative to the site, including the regulatory initiative, site description, and progress to date. Section 2 includes the summary of additional monitoring well installation activities and the results of baseline groundwater sampling. Section 3 presents the baseline hydrogeology and planned zone of influence for groundwater remediation

  18. Review of sensors for the in situ chemical characterization of the Hanford underground storage tanks

    International Nuclear Information System (INIS)

    Kyle, K.R.; Mayes, E.L.

    1994-01-01

    Lawrence Livermore National Laboratory (LLNL), in the Technical Task Plan (TTP) SF-2112-03 subtask 2, is responsible for the conceptual design of a Raman probe for inclusion in the in-tank cone penetrometer. As part of this task, LLNL is assigned the further responsibility of generating a report describing a review of sensor technologies other than Raman that can be incorporated in the in-tank cone penetrometer for the chemical analysis of the tank environment. These sensors would complement the capabilities of the Raman probe, and would give information on gaseous, liquid, and solid state species that are insensitive to Raman interrogation. This work is part of a joint effort involving several DOE laboratories for the design and development of in-tank cone penetrometer deployable systems for direct UST waste characterization at Westinghouse Hanford Company (WHC) under the auspices of the U.S. Department of Energy (DOE) Underground Storage Tank Integrated Demonstration (UST-ID)

  19. Safety issue resolution strategy plan for inactive miscellaneous underground storage tanks

    International Nuclear Information System (INIS)

    Wang, O.S.; Powers, T.B.

    1994-09-01

    The purpose of this strategy plan is to identify, confirm, and resolve safely issues associated with inactive miscellaneous underground storage tanks (MUSTs) using a risk-based priority approach. Assumptions and processes to assess potential risks and operational concerns are documented in this report. Safety issue priorities are ranked based on a number of considerations including risk ranking and cost effectiveness. This plan specifies work scope and recommends schedules for activities related to resolving safety issues, such as collecting historical data, searching for authorization documents, performing Unreviewed Safety Question (USQ) screening and evaluation, identifying safety issues, imposing operational controls and monitoring, characterizing waste contents, mitigating and resolving safety issues, and fulfilling other remediation requirements consistent with the overall Tank Waste Remediation System strategy. Recommendations for characterization and remediation are also recommended according to the order of importance and practical programmatic consideration

  20. Assessment of concentration mechanisms for organic wastes in underground storage tanks at Hanford

    International Nuclear Information System (INIS)

    Gerber, M.A.; Burger, L.L.; Nelson, D.A.; Ryan, J.L.; Zollars, R.L.

    1992-09-01

    Pacific Northwest Laboratory (PNL) has conducted an initial conservative evaluation of physical and chemical processes that could lead to significant localized concentrations of organic waste constituents in the Hanford underground storage tanks (USTs). This evaluation was part of ongoing studies at Hanford to assess potential safety risks associated with USTs containing organics. Organics in the tanks could pose a potential problem if localized concentrations are high enough to propagate combustion and are in sufficient quantity to produce a large heat and/or gas release if in contact with a suitable oxidant. The major sources of oxidants are oxygen in the overhead gas space of the tanks and sodium nitrate and nitrite either as salt cake solids or dissolved in the supernatant and interstitial liquids

  1. Non-uniform regulations of underground storage tanks in the United States

    International Nuclear Information System (INIS)

    Nadim, F.; Hoag, G.E.; Liu, S.; Carley, R.J.; Zack, P.

    2000-01-01

    Leaking underground storage tanks (USTs) are one of the major sources of ground water contamination. United States federal regulations for USTs were established in September of 1988. Since that time little or no amendments have been made to these regulations. In order to protect sensitive areas such as aquifer recharge zones for public water supply wells and wetlands, different states have been obligated to apply more stringent standards than the federal UST regulations. This practice however, has led to a non-uniform application of regulations for USTs throughout the country. In this article, United States regulations for USTs are reviewed and its deficits are highlighted. Based on these regulations and the experience of northeastern states of United States, a sequence of leak and spill preventive measures for USTs is proposed. Application of the proposed measures could substantially reduce the possibility of UST failure and would be more protective of the subsurface environment. (author)

  2. Underground gas storage Lobodice geological model development based on 3D seismic interpretation

    International Nuclear Information System (INIS)

    Kopal, L.

    2015-01-01

    Aquifer type underground gas storage (UGS) Lobodice was developed in the Central Moravian part of Carpathian foredeep in Czech Republic 50 years ago. In order to improve knowledge about UGS geological structure 3D seismic survey was performed in 2009. Reservoir is rather shallow (400 - 500 m below surface) it is located in complicated locality so limitations for field acquisition phase were abundant. This article describes process work flow from 3D seismic field data acquisition to geological model creation. The outcomes of this work flow define geometry of UGS reservoir, its tectonics, structure spill point, cap rock and sealing features of the structure. Improving of geological knowledge about the reservoir enables less risky new well localization for UGS withdrawal rate increasing. (authors)

  3. Acoustic imaging of underground storage tank wastes: A feasibility study. Final report

    International Nuclear Information System (INIS)

    Turpening, R.; Zhu, Z.; Caravana, C.; Matarese, J.

    1995-01-01

    The objectives for this underground storage tank (UST) imaging investigation are: (1) to assess the feasibility of using acoustic methods in UST wastes, if shown to be feasible, develop and assess imaging strategies; (2) to assess the validity of using chemical simulants for the development of acoustic methods and equipment. This investigation examined the velocity of surrogates, both salt cake and sludge surrogates. In addition collected seismic cross well data in a real tank (114-TX) on the Hanford Reservation. Lastly, drawing on the knowledge of the simulants and the estimates of the velocities of the waste in tank 114-TX the authors generated a hypothetical model of waste in a tank and showed that non-linear travel time tomographic imaging would faithfully image that stratigraphy

  4. Assessment of concentration mechanisms for organic wastes in underground storage tanks at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.A.; Burger, L.L.; Nelson, D.A.; Ryan, J.L. (Pacific Northwest Lab., Richland, WA (United States)); Zollars, R.L. (Washington State Univ., Pullman, WA (United States))

    1992-09-01

    Pacific Northwest Laboratory (PNL) has conducted an initial conservative evaluation of physical and chemical processes that could lead to significant localized concentrations of organic waste constituents in the Hanford underground storage tanks (USTs). This evaluation was part of ongoing studies at Hanford to assess potential safety risks associated with USTs containing organics. Organics in the tanks could pose a potential problem if localized concentrations are high enough to propagate combustion and are in sufficient quantity to produce a large heat and/or gas release if in contact with a suitable oxidant. The major sources of oxidants are oxygen in the overhead gas space of the tanks and sodium nitrate and nitrite either as salt cake solids or dissolved in the supernatant and interstitial liquids.

  5. Thermalhydraulic analyses of AECL's spent fuel dry storage systems

    International Nuclear Information System (INIS)

    Moffett, R.; Sabourin, G.

    1995-01-01

    This paper presents the validation of one- and three-dimensional thermalhydraulic models to be used to evaluate the thermal performance of AECL's MACSTOR and CANSTOR spent fuel dry storage modules. For this purpose, we compared analytical results to results of experiments conducted at AECL's Whiteshell Laboratories where mockups of the MACSTOR module and of a CANDU fuel storage basket were tested. The paper shows improvements to a simple one-dimensional model of the MACSTOR mock-up used previously. The replacement of constant heat transfer coefficients by free convection correlations, the addition of a storage cylinder model, and the addition of a radiation heat transfer model improved the predictions of concrete and storage cylinder temperatures. The paper also presents a new three-dimensional model for flow and heat transfer in the MACSTOR mock-up developed using CFDS-FLOW3D and -RAD3D computer programs. CFDS-FLOW3D code can estimate loss coefficients in complex geometry to an accuracy better than standard engineering correlations. The flow and temperature fields predicted using CFDS-FLOW3D are consistent with the measurements made during MACSTOR mock-up experiments (author). 5 refs., 4 tabs., 9 figs

  6. Development of a rapid screening protocol for selection of strains resistant to spray drying and storage in dry powder.

    Science.gov (United States)

    Reimann, S; Grattepanche, F; Baggenstos, C; Rezzonico, E; Berger, B; Arigoni, F; Lacroix, C

    2010-06-01

    An efficient screening method for selection of Bifidobacterium longum strains resistant to spray drying and storage was developed based on randomly amplified polymorphic DNA (RAPD) for identification of the best survivors in mixed strains bacterial preparations. Three different primers were used to generate RAPD profiles of 22 B. longum strains. All strains were distinguished according to their RAPD profiles except for the strain NCC2705 and its H(2)O(2) resistant derivative variant. The 22 strains were grouped in 3 batches of 7, 7 and 8 strains and subjected to spray drying and storage at 30 and 37 °C under anaerobic conditions. Batch survival rates after spray drying reached 17.1±4.4%. Strains showing the highest prevalence and/or resistance to storage at 37 °C were selected from individual batches for subsequent spray drying and storage testing. After 67 days of storage, NCC572 was identified as the dominant strain in powder. The stability of strain NCC572 was confirmed by performing single spray drying and storage tests. Out of 22 B. longum strains, a robust strain was identified by combining RAPD with a simultaneous screening test for survival under spray drying and storage. The method allowed a fast screening of B. longum strains in mixture for resistance to spray drying and storage compared to traditional screening procedures carried out with individual strains, in the same conditions. This approach could be applied to other stress conditions.

  7. Thermoelectric Powered Wireless Sensors for Dry-Cask Storage

    Science.gov (United States)

    Carstens, Thomas Alan

    This study focuses on the development of self-powered wireless sensors. These sensors can be used to measure key parameters in extreme environments; e.g., temperature monitoring for spent nuclear fuel during dry-cask storage. This study has developed a design methodology for these self-powered monitoring systems. The main elements that constitute this work consist of selecting and testing a power source for the wireless sensor, determination of the attenuation of the wireless signal, and testing the wireless sensor circuitry in an extreme environment. OrigenArp determined the decay heat and gamma/neutron source strength of the spent fuel throughout the service life of the dry-cask. A first principles analysis modeled the temperatures inside the dry-cask. A finite-element heat transfer code calculated the temperature distribution of the thermoelectric and heat sink. The temperature distributions determine the power produced by the thermoelectric. It was experimentally verified that a thermoelectric generator (HZ-14) with a DC/DC converter (Linear Technology LTC3108EDE) can power a transceiver (EmbedRF) at condition which represent prototypical conditions throughout and beyond the service life of the dry-cask. The wireless sensor is required to broadcast with enough power to overcome the attenuation from the dry-cask. It will be important to minimize the attenuation of the signal in order to broadcast with a small transmission power. To investigate the signal transmission through the dry-cask, CST Microwave Studio was used to determine the scattering parameter S2,1 for a horizontal dry-cask. Important parameters that can influence the transmission of the signal are antenna orientation, antenna placement, and transmission frequency. The thermoelectric generator, DC/DC converter, and transceiver were exposed to 60Co gamma radiation (exposure rate170.3 Rad/min) at the University of Wisconsin Medical Radiation Research Center. The effects of gamma radiation on the

  8. Advice on Sustainable Use of the Underground for Heat and Cold Storage; Advies Duurzaam Gebruik van de Bodem voor WKO

    Energy Technology Data Exchange (ETDEWEB)

    Oomes, J.

    2009-09-15

    Insights and ideas are given and discussed with regard to sustainable use of soil and underground for heat and cold storage. Also attention is paid to the marginal conditions for the application of heat and cold storage [Dutch] Inzichten en ideeen worden gegeven en besproken over duurzaam gebruik van de bodem voor warmte- koudeopslag (WKO). Daarnaast worden ook de randvoorwaarden van WKO in kaart gebracht.

  9. 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)

  10. Development of in-structure design spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Julyk, L.J.

    1995-09-01

    In-structure response spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site are developed on the basis of recent soil-structure-interaction analyses. Recommended design spectra are provided for various locations on the tank dome

  11. Root cause analysis of the fatigue failures of the pulsation dampers of a large underground gas storage (UGS) system

    NARCIS (Netherlands)

    Eijk, A.; Lange, D. de; Maljaars, J.; Tenbrock-Ingenhorst, A.; Gottmer, A.

    2014-01-01

    Two large identical 6-cylinder Ariel JGB/6 reciprocating compressors each of 7.5 MW, are used for an underground gas storage system (UGS) plant of RWE Gasspeicher GmbH located in Epe, Germany. The system is in operation since 2005. In 2011 several internals parts (baffle plates and baffle choke

  12. Estimated risk contribution for dry spent fuel storage cask

    International Nuclear Information System (INIS)

    Santos, C.; Kirk, M.T.; Abramson, L.; Guttmann, J.; Hackett, E.; Simonen, F.A.

    2001-01-01

    The U.S. Nuclear Regulatory Commission (NRC) is pursuing means to risk-inform its regulations and programs for dry storage of spent nuclear fuel. In pursuit of this objective, the NRC will develop safety goals and probabilistic risk assessments for implementing risk-informed programs. This paper provides one example method for calculating the risk of a dry spent fuel storage cask under normal and accident conditions. The example is on the HI-STORM 100 cask at a proposed site containing four thousand such casks. The paper evaluates the risk to the public by determining the likelihood a welded stainless steel container will leak. In addition, the study addresses the risk at a site where 4,000 casks may be stored until the U.S. Department of Energy accepts the casks for placement in a repository. The methods used employ the PRODIGAL computer code to assess the probability of a faulty weld on a stainless steel-welded canister. These analyses are only the initial stages of a comprehensive risk study that the NRC is performing in support of its regulatory initiatives. (author)

  13. Dry Cask Storage Inspection and Monitoring. Interim Report.

    Energy Technology Data Exchange (ETDEWEB)

    Bakhtiari, Susan [Argonne National Lab. (ANL), Argonne, IL (United States); Elmer, Thomas W. [Argonne National Lab. (ANL), Argonne, IL (United States); Koehl, Eugene R. [Argonne National Lab. (ANL), Argonne, IL (United States); Wang, Ke [Argonne National Lab. (ANL), Argonne, IL (United States); Raptis, Apostolos C. [Argonne National Lab. (ANL), Argonne, IL (United States); Kunerth, Dennis C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Birk, Sandra M. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-03-04

    Recently, the U.S. Nuclear Regulatory Commission (NRC) issued the guidance on the aging management of dry storage facilities that indicates the necessity to monitor the conditions of dry cask storage systems (DCSSs) over extended periods of time.1 Part of the justification of the aging management plans is the requirement for inspection and monitoring to verify whether continued monitoring, inspection or mitigation are necessary. To meet this challenge Argonne National Laboratory (ANL) in collaboration with Idaho National Laboratory (INL) is conducting scoping studies on current and emerging nondestructive evaluation/examination (NDE) and online monitoring (OLM) technologies for DCSS integrity assessments. The scope of work plan includes identification and verification of technologies for long-term online monitoring of DCSSs’ crucial physical parameters such as temperature, pressure, leakage and structural integrity in general. Modifications have been made to the current technologies to accommodate field inspections and monitoring. A summary of the scoping studies and experimental efforts conducted to date as well as plans for future activities is provided below.

  14. A comparative study of gas-gas miscibility processes in underground gas storage reservoirs

    Energy Technology Data Exchange (ETDEWEB)

    Rafiee, M.M.; Schmitz, S. [DBI - Gastechnologisches Institut gGmbH, Freiberg (Germany)

    2013-08-01

    Intermixture of gases in underground gas reservoirs have had great weight for natural gas storage in UGS projects with substitution of cushion gas by inert gases or changing the stored gas quality or origin, as for the replacement of town gas by natural gas. It was also investigated during the last years for Enhanced Gas Recovery (EGR) and Carbon Capture and Storage (CCS) projects. The actual importance of its mechanisms is discussed for the H{sub 2} storage in Power to Gas to Power projects (PGP). In these approaches miscibility of the injected gas with the gas in place in the reservoir plays an important role in the displacement process. The conditions and parameters for the gas-gas displacement and mixing have been investigated in previous projects, as e.g. the miscibility of CO{sub 2} with natural gas (CLEAN). Furthermore the miscibility process of town gas with natural gas and sauer gas with sweet gas were also previously measured and compared in laboratory. The objective of this work is to investigate the miscibility of H{sub 2} injection into natural gas reservoirs using a compositional and a black oil reservoir simulator. Three processes of convection, dispersion and diffusion are considered precisely. The effect of gas miscibility is studied for both simulators and the results are compared to find optimum miscibility parameters. The findings of this work could be helpful for further pilot and field case studies to predict and monitor the changes in gas composition and quality. In future this monitoring might become more important when PGP together with H{sub 2}-UGS, as storage technology, will help to successfully implement the change to an energy supply from more renewable sources. Similarly the method confirms the use of the black oil simulator as an alternative for gas-gas displacement and sequestration reservoir simulation in comparison to the compositional simulator. (orig.)

  15. Spray Drying of Spinach Juice: Characterization, Chemical Composition, and Storage.

    Science.gov (United States)

    Çalışkan Koç, Gülşah; Nur Dirim, Safiye

    2017-12-01

    The 1st aim of this study is to determine the influence of inlet and outlet air temperatures on the physical and chemical properties of obtained powders from spinach juice (SJ) with 3.2 ± 0.2 °Brix (°Bx). Second, the effect of 3 different drying agents (maltodextrin, whey powder, and gum Arabic) on the same properties was investigated for the selected inlet/outlet temperatures (160/100 °C) which gives the minimum moisture content and water activity values. For this purpose, the total soluble solid content of SJ was adjusted to 5.0 ± 0.2 °Bx with different drying agents. Finally, the effects of different storage conditions (4, 20, and 30 °C) on the physical and chemical properties of spinach powders (SPs) produced at selected conditions were examined. A pilot scale spray dryer was used at 3 different inlet/outlet air temperatures (160 to 200 °C/80 to 100 °C) where the outlet air temperature was controlled by regulating the feed flow rate. Results showed that the moisture content, water activity, browning index, total chlorophyll, and total phenolic contents of the SP significantly decreased and pH and total color change of the SP significantly increased by the addition of different drying agents (P < 0.05). In addition, the changes in the above-mentioned properties were determined during the storage period, at 3 different temperatures. It was also observed that the vitamin C, β-carotene, chlorophyll, and phenolic compounds retention showed first-order degradation kinetic with activation energy of 32.6840, 10.2736, 27.7031, and 28.2634 kJ/K.mol, respectively. © 2017 Institute of Food Technologists®.

  16. Enhanced Thermal Management System for Spent Nuclear Fuel Dry Storage Canister with Hybrid Heat Pipes

    International Nuclear Information System (INIS)

    Jeong, Yeong Shin; Bang, In Cheol

    2016-01-01

    Dry storage uses the gas or air as coolant within sealed canister with neutron shielding materials. Dry storage system for spent fuel is regarded as relatively safe and emits little radioactive waste for the storage, but it showed that the storage capacity and overall safety of dry cask needs to be enhanced for the dry storage cask for LWR in Korea. For safety enhancement of dry cask, previous studies of our group firstly suggested the passive cooling system with heat pipes for LWR spent fuel dry storage metal cask. As an extension, enhanced thermal management systems for the spent fuel dry storage cask for LWR was suggested with hybrid heat pipe concept, and their performances were analyzed in thermal-hydraulic viewpoint in this paper. In this paper, hybrid heat pipe concept for dry storage cask is suggested for thermal management to enhance safety margin. Although current design of dry cask satisfies the design criteria, it cannot be assured to have long term storage period and designed lifetime. Introducing hybrid heat pipe concept to dry storage cask designed without disrupting structural integrity, it can enhance the overall safety characteristics with adequate thermal management to reduce overall temperature as well as criticality control. To evaluate thermal performance of hybrid heat pipe according to its design, CFD simulation was conducted and previous and revised design of hybrid heat pipe was compared in terms of temperature inside canister

  17. Spent fuel and materials performance in wet and dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Zuloaga, P [ENRESA (Spain)

    2012-07-01

    According to the 6th General Radioactive Waste Plan, spent fuel in Spain shall have to be gathered in a Centralised Temporary Storage (CTS) during some decades in order to have time for a decision concerning its final fate: direct disposal at a geological repository or partitioning and transmutation if technology opens this possibility when the decision will be taken, expected in 2050. The CTS technology has already been chosen as a vault type building based in spent fuel dry storage. To support the use of this technology, a number of programmes have been completed or are still in progress, mostly concerned about high burnup fuel issues and new cladding materials. These programmes are directly managed by ENRESA alone or in joint venture with other parties, at a national and international level. Apart from that, there are contacts with other countries organisms who share similar interests with Spanish ones. The objectives are: Review of spent fuel data relevant for future storage in Spain; Perform destructive and non-destructive examinations on irradiated and non-irradiated fuel rods relevant to Spanish spent fuel management.

  18. Review of Current Criteria of Spent Fuel Rod Integrity during Dry Storage

    International Nuclear Information System (INIS)

    Yang, Yong Sik; Kim, Sun Ki; Bang, Je Geon; Song, Kun Woo

    2006-01-01

    A PWR spent fuel has been stored in a wet storage pool in Korea. However, the amount of spent fuel is expected to exceed the capacity of a wet storage pool within 10∼15 years. From the early 1970's, a research on the PWR spent fuel dry storage started because the dry storage system has been economical compared with the wet storage system. The dry storage technology for Zircaloy-clad fuel was assessed and licensed in many countries such as USA, Canada, FRG and Switzerland. In the dry storage system, a clad temperature may be higher than in the wet storage system and can reach up to 400 .deg.. A higher clad temperature can cause cladding failures during the period of dry storage, and thus a dry storage related research has essentially dealt with the prevention of clad degradation. It is temperature and rod internal pressure that cause cladding failures through the mechanisms such as clad creep rupture, hydride re-orientation, and stress-corrosion cracking etc.. In this paper, the current licensing criteria are summarized for the PWR spent fuel dry storage system, especially on spent fuel rod integrity. And it is investigated that an application propriety of existing criteria to Korea spent fuel dry storage system

  19. Operating experience of vault type dry storage and its relevance to future storage needs

    International Nuclear Information System (INIS)

    Maxwell, E.O.; Deacon, D.

    1982-01-01

    An outline description of the early passive cooled vault type dry stores for irradiated magnox fuel at the Wylfa Nuclear Power Station together with the valuable operating experience gained over many years. An outline description of the world's first air-cooled vault type dry store (350 Te) and comments on its construction and successful operation. A description of the basic principles that were used in the design of this store and how these principles have been developed for use on vault type storage systems for oxide fuel and vitrified waste. An examination of the basic parameters that the author's consider should be used to measure the adequacy of the many storage options currently being considered around the world is included in order that a better assessment of the various systems may be obtained

  20. Heat storage in underground caverns - measurements and simulations; Speicherung von Waerme in Grubenraeumen - Messung und Simulation

    Energy Technology Data Exchange (ETDEWEB)

    Schaberg, A; Krause, H; Poetke, W [TU Bergakademie Freiberg (Germany). Inst. fuer Waermetechnik und Technische Thermodynamik

    1997-12-01

    Among the different discussed underground concepts for longterm storing of solar or waste heat old waterfilled mines can be an interesting solution. To examine the temperature behaviour of this storage type a testing store is built in a mine belonging to the Freiberg University of Mining and Technology in Saxonia. In a longterm project temperatures are measured inside the water volume and in the adjacent rock. The temperature behaviour depends on the operating conditions. Inside the water volume temperature stratification can be observed. During loading and standstill heat is transported into the rock surrounding. A certain part of this amount of heat can be discharged again. For designing and optimizing this storage type a numerical modell is developed. The modell is validated with experimental data from the testing plant. (orig.) [Deutsch] Unter den verschiedenen, in der Diskussion stehenden Untegrund-Waermespeichern fuer Solarwaerme oder Abwaerme bieten sich auch geflutete Gruben als Waermespeicher an. Zur Untersuchung des Temperaturverhaltens dieses Speichertyps ist im Saechsischen Lehr- und Besucherbergwerk der TU Bergakademie Freiberg ein Versuchsspeicher errichtet worden. In einem Langzeitversuch wird das Temperaturfeld im Wasser und im angrenzenden Gestein aufgezeichnet. Das Temperaturverhalten ist von den Betriebsgroessen abhaengig. Im Grubenwasser stellt sich eine stabile Temperaturschichtung ein. Waehrend der Beladung und der Stillstandszeiten wird Waerme in die Gesteinsumgebung transportiert. Ein Teil dieser Waermemenge kann wider entspeichert werden. Zur Auslegung und Optimierung von Gruben-Waermespeichern ist ein numerisches Modell entwickelt worden. Das Modell ist anhand der Messergebnisse des Versuchsspeichers validiert worden. (orig.)

  1. Waste Isolation Pilot Plant supplementary roof support system underground storage area, Panel 1, Room 1

    International Nuclear Information System (INIS)

    1991-10-01

    WIPP is designed to provide a full-scale facility to demonstrate the technical and operational principles for permanent isolation of defense-generated transuranic waste. It is also designed to provide a facility in which studies and experiments can be conducted. Bin Scale Tests are being planned as part of the WIPP Test Phase Performance Assessment Program described in the WIPP Test Phase Plan: Performance Assessment (DOE 1990 b). These Tests are anticipated to be conducted over a period of up to seven years. Room 1 of Panel 1 of the Underground Storage Area is to be used as the location of the Bin-Scale Tests to investigate the generation of gas from the waste that is proposed to be stored at the WIPP in the near future. The original design for the waste storage rooms in Panel 1 provided for a limited period of time during which to mine the openings and to emplace waste. Room 1 was initially mined to rough dimensions in 1986. Information obtained from the Site and Preliminary Design Validation (SPDV) program showed that the rooms would remain stable without ground support and that creep closure would not adversely affect equipment clearances during at least five years following excavation

  2. Cryograb: A Novel Approach to the Retrieval of Waste from Underground Storage Tanks - 13501

    Energy Technology Data Exchange (ETDEWEB)

    O' Brien, Luke; Baker, Stephen; Bowen, Bob [UK National Nuclear Laboratory, Chadwick House, Warrington (United Kingdom); Mallick, Pramod; Smith, Gary [US Department of Energy (United States); King, Bill [Savannah River National Laboratory (United States); Judd, Laurie [NuVision Engineering (United States)

    2013-07-01

    The UK's National Nuclear Laboratory (NNL) is investigating the use of cryogenic technology for the recovery of nuclear waste. Cryograb, freezing the waste on a 'cryo-head' and then retrieves it as a single mass which can then be treated or stabilized as necessary. The technology has a number of benefits over other retrieval approaches in that it minimizes sludge disturbance thereby reducing effluent arising and it can be used to de-water, and thereby reduce the volume of waste. The technology has been successfully deployed for a variety of nuclear and non-nuclear waste recovery operations. The application of Cryograb for the recovery of waste from US underground storage tanks is being explored through a US DOE International Technology Transfer and Demonstration programme. A sample deployment being considered involves the recovery of residual mounds of sludge material from waste storage tanks at Savannah River. Operational constraints and success criteria were agreed prior to the completion of a process down selection exercise which specified the preferred configuration of the cryo-head and supporting plant. Subsequent process modeling identified retrieval rates and temperature gradients through the waste and tank infrastructure. The work, which has been delivered in partnership with US DOE, SRNL, NuVision Engineering and Frigeo AB has demonstrated the technical feasibility of the approach (to TRL 2) and has resulted in the allocation of additional funding from DOE to take the programme to bench and cold pilot-scale trials. (authors)

  3. Technical issues and approach to license dry storage of LWR fuel in the United States

    International Nuclear Information System (INIS)

    Johnson, A.B.; Beeman, G.H.; Creer, J.M.; Gilbert, E.R.

    1984-01-01

    Dry storage is emerging as an important alternative to wet storage for US utilities, even though wet storage will remain the principal storage method, at least until the federal government begins to accept fuel in 1998. Dry storage has been licensed in several countries. In the USA, dry storage issues are related to storage system performance and behavior of spent fuel during storage. There is a coordinated US effort among electric utilities, the Electric Power Research Institute (EPRI), the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC) to license two dry storage concepts: metal casks, and horizontal storage modules. The following activities are underway to resolve the licensing issues associated with dry storage and to establish the licensing basis: a) summarize and assimilate domestic and foreigh dry storage experience; b) conduct tests which resolve specific licensing issues; c) conduct cooperative demonstrations of the leading dry storage concepts; d) establish criteria and justifications for generic licensing. The paper summarizes the licensing issues and the approach to their resolution

  4. Report on technical feasibility of underground pumped hydroelectric storage in a marble quarry site in the Northeast United States

    Energy Technology Data Exchange (ETDEWEB)

    Chas. T. Main, Inc.

    1982-03-01

    The technical and economic aspects of constructing a very high head underground hydroelectric pumped storage were examined at a prefeasibility level. Excavation of existing caverns in the West Rutland Vermont marble quarry would be used to construct the underground space. A plant capacity of 1200 MW and 12 h of continuous capacity were chosen as plant operating conditions. The site geology, plant design, and electrical and mechanical equipment required were considered. The study concluded that the cost of the 1200 MW underground pumped storage hydro electric project at this site even with the proposed savings from marketable material amounts to between $581 and $595 per kilowatt of installed capacity on a January 1982 pricing level. System studies performed by the planning group of the New England Power System indicate that the system could economically justify up to about $442 per kilowatt on an energy basis with no credit for capacity. To accommodate the plant with the least expensive pumping energy, a coal and nuclear generation mix of approximately 65% would have to be available before the project becomes feasible. It is not expected that this condition can be met before the year 2000 or beyond. It is therefore concluded that the West Rutland underground pumped storage facility is uneconomic at this time. Several variables however could have marked influence on future planning and should be examined on periodic basis.

  5. Storage of oil above ground for underground: Regulations, costs, and risks

    International Nuclear Information System (INIS)

    Lively-Diebold, B.; Driscoll, W.; Ameer, P.; Watson, S.

    1993-01-01

    Some owners of underground storage tank systems (USTs) appear to be replacing their systems with aboveground storage tank systems (ASTs) without full knowledge of the US Government environmental regulations that apply to facilities with ASTs, and their associated costs. This paper discusses the major federal regulatory requirements for USTs and ASTS, and presents the compliance costs for new tank systems that range in capacity from 1,000 to 10,000 gallons. The costs of two model UST system and two model AST systems are considered for new oil storage capacity, expansion of existing capacity, and replacement of an existing UST or AS T. For new capacity, ASTs are less expensive than USTs, although ASTs do have significant regulatory compliance costs that range from an estimated $8,000 to $14,000 in present value terms, depending on the size and type of system. For expanded or replacement capacity, ASTs are in all but one case less expensive than USTS; the exception is the expansion of capacity at an existing UST facility. In this case, the cost of a protected steel tank UST system is comparable to the cost of an AST system. Considering the present value of all costs over a 30 year useful life, the cost for an AST with a concrete dike is less than the cost of an AST with an earthen dike, for the tank sizes considered. This is because concrete dikes are cost competitive for small tanks, and the costs to clean up a release are higher for earthen dikes, due to the cost of disposal and replacement of oil-contaminated soil. The cost analyses presented here are not comprehensive, and are intended primarily for illustrative purposes. Only the major costs of tank purchase, installation, and regulatory compliance were considered

  6. The role of the underground for massive storage of energy: a preliminary glance of the French case

    Science.gov (United States)

    Audigane, Pascal; Gentier, Sylvie; Bader, Anne-Gaelle; Beccaletto, Laurent; Bellenfant, Gael

    2014-05-01

    The question of storing energy in France has become of primary importance since the launch of a road map from the government which places in pole position this topic among seven major milestones to be challenged in the context of the development of innovative technology in the country. The European objective to reach 20% of renewables in the energy market, from which a large part would come from wind and solar power generation, raises several issues regarding the capacity of the grid to manage the various intermittent energy sources in line with the variability of the public demand and offer. These uncertainties are highly influenced by unpredictable weather and economic fluctuations. To facilitate the large-scale integration of variable renewable electricity sources in grids, massive energy storage is needed. In that case, electric energy storage techniques involving the use of underground are often under consideration as they offer a large storage capacity volume with a adapted potential of confining and the space required for the implantation. Among the panel of massive storage technologies, one can find (i) the Underground Pumped Hydro-Storage (UPHS) which are an adaptation of classical Pumped Hydro Storage system often connected with dam constructions, (ii) the compressed air storage (CAES) and (iii) the hydrogen storage from conversion of electricity into H2 and O2 by electrolysis. UPHS concept is based on using the potential energy between two water reservoirs positioned at different heights. Favorable natural locations like mountainous areas or cliffs are spatially limited given the geography of the territory. This concept could be extended with the integration of one of these reservoirs in an underground cavities (specifically mined or reuse of preexisting mines) to increase opportunities on the national territory. Massive storage based on compression and relaxation of air (CAES) requires high volume and confining pressure around the storage that exists

  7. Geomechanical Analysis of Underground Coal Gasification Reactor Cool Down for Subsequent CO2 Storage

    Science.gov (United States)

    Sarhosis, Vasilis; Yang, Dongmin; Kempka, Thomas; Sheng, Yong

    2013-04-01

    Underground coal gasification (UCG) is an efficient method for the conversion of conventionally unmineable coal resources into energy and feedstock. If the UCG process is combined with the subsequent storage of process CO2 in the former UCG reactors, a near-zero carbon emission energy source can be realised. This study aims to present the development of a computational model to simulate the cooling process of UCG reactors in abandonment to decrease the initial high temperature of more than 400 °C to a level where extensive CO2 volume expansion due to temperature changes can be significantly reduced during the time of CO2 injection. Furthermore, we predict the cool down temperature conditions with and without water flushing. A state of the art coupled thermal-mechanical model was developed using the finite element software ABAQUS to predict the cavity growth and the resulting surface subsidence. In addition, the multi-physics computational software COMSOL was employed to simulate the cavity cool down process which is of uttermost relevance for CO2 storage in the former UCG reactors. For that purpose, we simulated fluid flow, thermal conduction as well as thermal convection processes between fluid (water and CO2) and solid represented by coal and surrounding rocks. Material properties for rocks and coal were obtained from extant literature sources and geomechanical testings which were carried out on samples derived from a prospective demonstration site in Bulgaria. The analysis of results showed that the numerical models developed allowed for the determination of the UCG reactor growth, roof spalling, surface subsidence and heat propagation during the UCG process and the subsequent CO2 storage. It is anticipated that the results of this study can support optimisation of the preparation procedure for CO2 storage in former UCG reactors. The proposed scheme was discussed so far, but not validated by a coupled numerical analysis and if proved to be applicable it could

  8. Analysis of fuel oxidation for long-term dry storage

    International Nuclear Information System (INIS)

    Dehaudt, Ph.

    1999-01-01

    Dry storage is one of the temporary end of life channels for PWR fuel assemblies after leaving the reactor. According to results of currently available digital simulations, the residual power will maintain at a temperature of over 150 degrees Celsius for several years for UO 2 and several decades for MOX. At such temperatures, the UO 2 , which constitutes the fuel wholly or partially (MOX) can oxidise in the presence of air to form the compound U 3 O 8 . The paper discusses parameters that influence the evolution of compounds formed as the reaction progresses, the morphological transformations accompanying their formation and the kinetic conditions according to the temperature and the nature of the initial products

  9. Construction of JRR-3 spent fuel dry storage facility

    International Nuclear Information System (INIS)

    Adachi, M.

    1982-01-01

    To store the JRR-3 metallic natural uranium spent fuel elements, dry storage facility has been constructed in JAERI. This facility has a capacity of about 30T of uranium. The elements are placed in encapsulated canister, then stored in drywell in the store. The store is basically an ordinary concrete box, about 12m long, 13m wide, and 5m deep. The store comprises a 10 x 10 lattice array of the drywells. The drywell consists of a stainless steel liner which is 2.5m deep, 36cm ID and 0.8cm thickness. A drywell also has an air inlet, outlet pipe for radiation monitoring and a shield plug in carbon steel for radiation protection. A canister which consists of stainless steel with 0.5cm thickness contains 36 elements. Sealing of the canister is accomplished by fusion welding

  10. Dry storage assessment of LWR fuel in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Goll, W [AREVA NP GmbH (Germany)

    2012-07-01

    Germany's revised energy act, dated 2002, prohibits the shipment of spent nuclear fuel to reprocessing plants and restricts its disposal to a final repository. To comply with this law and to ensure further nuclear plant operation, the reactor operators had to construct on-site facilities for dry cask storage, to keep spent fuel assemblies for 40 years until a final repository is available. Twelve facilities went into operation during the last years. The amount of spent fuel in store is continuously increasing and has reached a level of about 1700 t HM by end of 2007. The central sites Ahaus and Gorleben remain in operation but shall be used for special purposes in future. The objectives are: Review of main features of facilities with an emphasis on associated monitoring; Review of degradation mechanisms in the context of fuel types and design (PWR, BWR, UO2, MOX) relative to fuel burn-up, structural materials and long term behaviour.

  11. Studies and research concerning BNFP: spent fuel dry storage studies at the Barnwell Nuclear Fuel Plant

    International Nuclear Information System (INIS)

    Anderson, K.J.

    1980-09-01

    Conceptual designs are presented utilizing the Barnwell Nuclear Fuel Plant for the dry interim storage of spent light water reactor fuel. Studies were conducted to determine feasible approaches to storing spent fuel by methods other than wet pool storage. Fuel that has had an opportunity to cool for several years, or more, after discharge from a reactor is especially adaptable to dry storage since its thermal load is greatly reduced compared to the thermal load immediately following discharge. A thermal analysis was performed to help in determining the feasibility of various spent fuel dry storage concepts. Methods to reject the heat from dry storage are briefly discussed, which include both active and passive cooling systems. The storage modes reviewed include above and below ground caisson-type storage facilities and numerous variations of vault, or hot cell-type, storage facilities

  12. Radiological protection for spent fuel dry storage at Embalse NPP

    International Nuclear Information System (INIS)

    Carballo, Carlos; Melo, Rodolfo

    2008-01-01

    Embalse NPP dry-stores used fuel elements in concrete silos inside the premises: The fuel elements are kept for at least 6 years in pools located in the controlled area , before being moved into the silos. This paper describes the radiological protection for the different stages of the process, i.e., when the used fuel elements are moved from the pools into the silos, and while they are kept in the concrete silos. The occupational exposure of the personnel operating this system at each stage is showed, as well as the environmental dose rates around the silos, and the dose rate in the shields used during the transfer. These environmental dose rates are assessed with portable instruments and with TLD dosimeters placed around the silos. This paper also describes the periodical routine control performed every two years in the atmosphere inside the silo, the moisture control and the detection of possible aerosols (in some cases, traces of krypton 85 were detected). It is important to point out that the maximum equivalent environmental dose rate H* (10) detected at approximately 20 metres from the silos is overly low: (0.35 micro sievert / hour). Our experience demonstrates that dry storage is totally compatible with the environment and with the ALARA criterion for personnel's doses. (author)

  13. UNDERGROUND AIR DUCT TO CONTROL RISING MOISTURE IN HISTORIC BUILDINGS: IMPROVED DESIGN AND ITS DRYING EFFICIENCY

    Directory of Open Access Journals (Sweden)

    Jiří Pazderka

    2017-10-01

    Full Text Available The underground air ducts along peripheral walls of a building are a remediation method, which principle is to enable an air flow along the moist building structure’s surface to allow a sufficient evaporation of moisture from the structure. This measure reduces the water transport (rising moisture into the higher parts of the wall where the high water content in masonry is undesirable. Presently, underground air ducts are designed as masonry structures, which durability in contact with ground moisture is limited. The article describes a new design of an underground air duct, which is based on specially shaped concrete blocks (without wet processes, because the blocks are completely precast. The air duct from concrete blocks is situated completely below the ground surface (exterior or below the floor (interior. Thanks to this, the system is invisible and does not disturb the authentic look of rehabilitated historic buildings. The efficiency of the air duct technical solution was verified by the results of tests (based on the measured moisture values conducted on a laboratory model. The experimental study showed that the moisture in the masonry equipped with the presented underground air duct had decreased considerably compared to the reference sample, namely by 43 % on average. The experimental study was numerically validated through numerical simulations performed with the program WUFI 2D.

  14. Seismic Performance of Dry Casks Storage for Long- Term Exposure

    Energy Technology Data Exchange (ETDEWEB)

    Ibarra, Luis [Univ. of Utah, Salt Lake City, UT (United States); Sanders, David [Univ. of Nevada, Reno, NV (United States); Yang, Haori [Oregon State Univ., Corvallis, OR (United States); Pantelides, Chris [Univ. of Utah, Salt Lake City, UT (United States)

    2016-12-30

    The main goal of this study is to evaluate the long-term seismic performance of freestanding and anchored Dry Storage Casks (DSCs) using experimental tests on a shaking table, as well as comprehensive numerical evaluations that include the cask-pad-soil system. The study focuses on the dynamic performance of vertical DSCs, which can be designed as free-standing structures resting on a reinforced concrete foundation pad, or casks anchored to a foundation pad. The spent nuclear fuel (SNF) at nuclear power plants (NPPs) is initially stored in fuel-storage pools to control the fuel temperature. After several years, the fuel assemblies are transferred to DSCs at sites contiguous to the plant, known as Interim Spent Fuel Storage Installations (ISFSIs). The regulations for these storage systems (10 CFR 72) ensure adequate passive heat removal and radiation shielding during normal operations, off-normal events, and accident scenarios. The integrity of the DSCs is important, even if the overpack does not breach, because eventually the spent fuel-rods need to be shipped either to a reprocessing plant or a repository. DSCs have been considered as a temporary storage solution, and usually are licensed for 20 years, although they can be relicensed for operating periods of up to 60 years. In recent years, DSCs have been reevaluated as a potential mid-term solution, in which the operating period may be extended for up to 300 years. At the same time, recent seismic events have underlined the significant risks DSCs are exposed. The consideration of DCSs for storing spent fuel for hundreds of years has created new challenges. In the case of seismic hazard, longer-term operating periods not only lead to larger horizontal accelerations, but also increase the relative effect of vertical accelerations that usually are disregarded for smaller seismic events. These larger seismic demands could lead to casks sliding and tipping over, impacting the concrete pad or adjacent casks. The casks

  15. Waterproofing shielding for concrete in wet and dry storage

    International Nuclear Information System (INIS)

    Gorin, N.; Scherbina, A.; Urusov, S.

    2007-01-01

    One of main reliability and safety criteria for constructions, designed for wet and dry storage of radioactive materials and waste, is the long-term ability to maintain the waterproofing properties in the conditions of high radiation load. The base structural material of these constructions is concrete (cooling ponds, different storage for spent nuclear fuel and waste, etc.). The provision of reliable concrete waterproofing is very important for decreasing risks of radioactive substances ingress to environment and moisture penetration to objects from outside, and also for construction life extension. In the process of long-term operation, some concrete constructions, erected already few decades ago, are gradually losing their waterproofing and this circumstance involves severe operational and ecological threats. Therefore advanced effective concrete waterproofing technologies both for erection of new objects and for repairing of operating constructions are in extreme demand. The paper is devoted to the solution of this problem proposed by Russian Federal Nuclear Centre (RFNC-VNIITF, Snezhinsk). The paper contains the developed criteria established for the search for optimal materials, the 'integral capillary systems' (ICS) principal of operation, methods and results of the tests, and also the experience of ICS application on real objects. (author)

  16. Integrity of spent CANDU fuel during and following dry storage

    International Nuclear Information System (INIS)

    Villagran, J.E.

    2004-01-01

    This report examines the issue of CANDU fuel integrity at the back end of the fuel cycle and outlines a program designed to provide assurance that used CANDU fuel will retain its integrity over an extended period. In specific terms, the program is intended to provide assurance that during and following extended dry storage the fuel will remain fit to undergo, without loss of integrity, the handling, packaging and transportation operations that might be necessary until it is placed in disposal containers. The first step in the development of the program was a review of the available technical information on phenomena relevant to fuel integrity. The major conclusions from that review were the following: Under normal storage conditions it is unlikely that the spent fuel will suffer significant degradation during a one-hundred year period and it should be possible to retrieve, repackage and transport the fuel as required, using methods and systems similar to those used today. However, to provide increased confidence regarding the above conclusion, investigations should be conducted in areas where there is higher uncertainty in the prediction of fuel condition and on some degradation processes to which the fuel appears to present higher vulnerability. The proposed program includes, among other tasks, irradiated fuel tests, analytical studies on the most relevant fuel degradation processes and the development of a long-term fuel verification program. (Author)

  17. Status of work at PNL supporting dry storage of spent fuel

    International Nuclear Information System (INIS)

    Cunningham, M.E.; McKinnon, M.A.; Michener, T.E.; Thomas, L.E.; Thornhill, C.K.

    1992-01-01

    Three projects related to dry storage of light-water reactor spent fuel are being conducted at Pacific Northwest Laboratory. Performance testing of six dry storage systems (four metal casks and two concrete storage systems) has been completed and results compiled. Two computer codes for predicting spent fuel and storage system thermal performance, COBRA-SFS and HYDRA-II, have been developed and have been reviewed by the US Nuclear Regulatory Commission. Air oxidation testing of spent fuel was conducted from 1984 through 1990 to obtain data to support recommendations of temperature-time limits for air dry storage for periods up to 40 years

  18. Underground Pumped Storage Hydropower using abandoned open pit mines: influence of groundwater seepage on the system efficiency

    Science.gov (United States)

    Pujades, Estanislao; Bodeux, Sarah; Orban, Philippe; Dassargues, Alain

    2016-04-01

    Pumped Storage Hydropower (PSH) plants can be used to manage the production of electrical energy according to the demand. These plants allow storing and generating electricity during low and high demand energy periods, respectively. Nevertheless, PSH plants require a determined topography because two reservoirs located at different heights are needed. At sites where PSH plants cannot be constructed due to topography requirements (flat regions), Underground Pumped Storage Hydropower (UPSH) plants can be used to adjust the electricity production. These plants consist in two reservoirs, the upper one is located at the surface (or at shallow depth) while the lower one is underground (or deeper). Abandoned open pit mines can be used as lower reservoirs but these are rarely isolated. As a consequence, UPSH plants will interact with surrounding aquifers exchanging groundwater. Groundwater seepage will modify hydraulic head inside the underground reservoir affecting global efficiency of the UPSH plant. The influence on the plant efficiency caused by the interaction between UPSH plants and aquifers will depend on the aquifer parameters, underground reservoir properties and pumping and injection characteristics. The alteration of the efficiency produced by the groundwater exchanges, which has not been previously considered, is now studied numerically. A set of numerical simulations are performed to establish in terms of efficiency the effects of groundwater exchanges and the optimum conditions to locate an UPSH plant.

  19. (Per)chlorate reduction by an acetogenic bacterium, Sporomusa sp., isolated from an underground gas storage.

    KAUST Repository

    Balk, Melike; Mehboob, Farrakh; van Gelder, Antonie H; Rijpstra, W Irene C; Damsté , Jaap S Sinninghe; Stams, Alfons J M

    2010-01-01

    A mesophilic bacterium, strain An4, was isolated from an underground gas storage reservoir with methanol as substrate and perchlorate as electron acceptor. Cells were Gram-negative, spore-forming, straight to curved rods, 0.5-0.8 microm in diameter, and 2-8 microm in length, growing as single cells or in pairs. The cells grew optimally at 37 degrees C, and the pH optimum was around 7. Strain An4 converted various alcohols, organic acids, fructose, acetoin, and H(2)/CO(2) to acetate, usually as the only product. Succinate was decarboxylated to propionate. The isolate was able to respire with (per)chlorate, nitrate, and CO(2). The G+C content of the DNA was 42.6 mol%. Based on the 16S rRNA gene sequence analysis, strain An4 was most closely related to Sporomusa ovata (98% similarity). The bacterium reduced perchlorate and chlorate completely to chloride. Key enzymes, perchlorate reductase and chlorite dismutase, were detected in cell-free extracts.

  20. (Per)chlorate reduction by an acetogenic bacterium, Sporomusa sp., isolated from an underground gas storage.

    KAUST Repository

    Balk, Melike

    2010-08-03

    A mesophilic bacterium, strain An4, was isolated from an underground gas storage reservoir with methanol as substrate and perchlorate as electron acceptor. Cells were Gram-negative, spore-forming, straight to curved rods, 0.5-0.8 microm in diameter, and 2-8 microm in length, growing as single cells or in pairs. The cells grew optimally at 37 degrees C, and the pH optimum was around 7. Strain An4 converted various alcohols, organic acids, fructose, acetoin, and H(2)/CO(2) to acetate, usually as the only product. Succinate was decarboxylated to propionate. The isolate was able to respire with (per)chlorate, nitrate, and CO(2). The G+C content of the DNA was 42.6 mol%. Based on the 16S rRNA gene sequence analysis, strain An4 was most closely related to Sporomusa ovata (98% similarity). The bacterium reduced perchlorate and chlorate completely to chloride. Key enzymes, perchlorate reductase and chlorite dismutase, were detected in cell-free extracts.

  1. Development of simulated tank wastes for the US Department of Energy's Underground Storage Tank Integrated Demonstration

    International Nuclear Information System (INIS)

    Elmore, M.R.; Colton, N.G.; Jones, E.O.

    1992-08-01

    The purpose of the Underground Storage Tank Integrated Demonstration (USTID) is to identify and evaluate technologies that may be used to characterize, retrieve, treat, and dispose of hazardous and radioactive wastes contained in tanks on US Department of Energy sites. Simulated wastes are an essential component of the evaluation process because they provide controlled samples for technology assessment, and minimize costs and risks involved when working with radioactive wastes. Pacific Northwest Laboratory has developed a recipe to simulate Hanford single-shell tank, (SST) waste. The recipe is derived from existing process recipes, and elemental concentrations are based on characterization data from 18 SSTs. In this procedure, salt cake and metal oxide/hydroxide sludge are prepared individually, and mixed together at varying ratios depending on the specific tank, waste to be simulated or the test being conducted. Elemental and physical properties of the stimulant are comparable with analyzed tank samples, and chemical speciation in the simulant is being improved as speciation data for actual wastes become available. The nonradioactive chemical waste simulant described here is useful for testing technologies on a small scale

  2. Revised cost savings estimate with uncertainty for enhanced sludge washing of underground storage tank waste

    International Nuclear Information System (INIS)

    DeMuth, S.

    1998-01-01

    Enhanced Sludge Washing (ESW) has been selected to reduce the amount of sludge-based underground storage tank (UST) high-level waste at the Hanford site. During the past several years, studies have been conducted to determine the cost savings derived from the implementation of ESW. The tank waste inventory and ESW performance continues to be revised as characterization and development efforts advance. This study provides a new cost savings estimate based upon the most recent inventory and ESW performance revisions, and includes an estimate of the associated cost uncertainty. Whereas the author's previous cost savings estimates for ESW were compared against no sludge washing, this study assumes the baseline to be simple water washing which more accurately reflects the retrieval activity along. The revised ESW cost savings estimate for all UST waste at Hanford is $6.1 B ± $1.3 B within 95% confidence. This is based upon capital and operating cost savings, but does not include development costs. The development costs are assumed negligible since they should be at least an order of magnitude less than the savings. The overall cost savings uncertainty was derived from process performance uncertainties and baseline remediation cost uncertainties, as determined by the author's engineering judgment

  3. Underground storage tank management plan, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    The Underground Storage Tank (UST) Program at the Oak Ridge Y-12 Plant was established to locate UST systems at the facility and to ensure that all operating UST systems are free of leaks. UST systems have been removed or upgraded in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance. With the closure of a significant portion of the USTs, the continuing mission of the UST Management Program is to manage the remaining active UST systems and continue corrective actions in a safe regulatory compliant manner. This Program outlines the compliance issues that must be addressed, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Program provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. The plan is divided into three major sections: (1) regulatory requirements, (2) active UST sites, and (3) out-of-service UST sites. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Program, and the procedures and guidance for compliance.

  4. Underground storage tank management plan, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1997-09-01

    The Underground Storage Tank (UST) Program at the Oak Ridge Y-12 Plant was established to locate UST systems at the facility and to ensure that all operating UST systems are free of leaks. UST systems have been removed or upgraded in accordance with Tennessee Department of Environment and Conservation (TDEC) regulations and guidance. With the closure of a significant portion of the USTs, the continuing mission of the UST Management Program is to manage the remaining active UST systems and continue corrective actions in a safe regulatory compliant manner. This Program outlines the compliance issues that must be addressed, reviews the current UST inventory and compliance approach, and presents the status and planned activities associated with each UST system. The UST Program provides guidance for implementing TDEC regulations and guidelines for petroleum UST systems. The plan is divided into three major sections: (1) regulatory requirements, (2) active UST sites, and (3) out-of-service UST sites. These sections describe in detail the applicable regulatory drivers, the UST sites addressed under the Program, and the procedures and guidance for compliance

  5. Steam reforming as a method to treat Hanford underground storage tank (UST) wastes

    International Nuclear Information System (INIS)

    Miller, J.E.; Kuehne, P.B.

    1995-07-01

    This report summarizes a Sandia program that included partnerships with Lawrence Livermore National Laboratory and Synthetica Technologies, Inc. to design and test a steam reforming system for treating Hanford underground storage tank (UST) wastes. The benefits of steam reforming the wastes include the resolution of tank safety issues and improved radionuclide separations. Steam reforming destroys organic materials by first gasifying, then reacting them with high temperature steam. Tests indicate that up to 99% of the organics could be removed from the UST wastes by steam exposure. In addition, it was shown that nitrates in the wastes could be destroyed by steam exposure if they were first distributed as a thin layer on a surface. High purity alumina and nickel alloys were shown to be good candidates for materials to be used in the severe environment associated with steam reforming the highly alkaline, high nitrate content wastes. Work was performed on designing, building, and demonstrating components of a 0.5 gallon per minute (gpm) system suitable for radioactive waste treatment. Scale-up of the unit to 20 gpm was also considered and is feasible. Finally, process demonstrations conducted on non-radioactive waste surrogates were carried out, including a successful demonstration of the technology at the 0.1 gpm scale

  6. Site-specific issues related to structural/seismic design of an underground independent spent fuel storage installation (ISFSI)

    International Nuclear Information System (INIS)

    Tripathi, B.P.

    2005-01-01

    Utilities owning and operating commercial nuclear power plants (NPP) in USA may choose to build an underground Independent Spent Fuel Storage Installation (ISFSI) to store the spent nuclear fuels. The regulatory requirements and other guidance are based on 10 CFR Part 72, Regulatory Guide RG 3.73, Standard Review Plans NUREG-1536 and NUREG-1567, and Interim staff Guidance (ISG) documents as applicable. Structures, Systems, and Components (SSCs) classified as important to safety are designed to withstand the effects of site-specific environmental conditions and natural phenomena such as earthquake, tornado, flood, etc. An underground ISFSI for storage of spent nuclear fuel, presents some unique analysis and design challenges. This paper will briefly address some of these challenges and discuss site-specific loads, including seismic for the ISFSI design. (authors)

  7. Safety aspects of dry spent fuel storage and spent fuel management

    International Nuclear Information System (INIS)

    Botsch, W.; Smalian, S.; Hinterding, P.; Voelzke, H.; Wolff, D.; Kasparek, E.

    2014-01-01

    The storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Safety aspects like safe enclosure of radioactive materials, safe removal of decay heat, nuclear criticality safety and avoidance of unnecessary radiation exposure must be achieved throughout the storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. In Germany dual purpose casks for SF or HLW are used for safe transportation and interim storage. TUV and BAM, who work as independent experts for the competent authorities, present the storage licensing process including sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields (authors)

  8. Investigation in order to precisely calculate the state of the air in dry underground mines

    Energy Technology Data Exchange (ETDEWEB)

    Aner, L; Krause, D; Schmidt, J

    1978-05-01

    A comparison between the calculation methods of Koenig, Batzel, Boldizsar, Mundry, Voss and Woropaew was made with data recorded in a test underground roadway over a period of one year. Precise measuring instruments were used, particularly for temperature measurement. The analysis and accompanying graphs show deviations in the results of the six calculation methods. A new mathematical formula is proposed, its parameters and a guide for application are given.

  9. Management of dry flue gas desulfurization by-products in underground mines

    Energy Technology Data Exchange (ETDEWEB)

    Sevim, H.

    1997-06-01

    Disposal of coal combustion by-products (CCBs) in an environmentally sound manner is a major issue facing the coal and utility industries in the US today. Disposal into abandoned sections of underground coal mines may overcome many of the surface disposal problems along with added benefits such as mitigation of subsidence and acid mine drainage. However, many of the abandoned underground coal mines are located far from power plants, requiring long distance hauling of by-products which will significantly contribute to the cost of disposal. For underground disposal to be economically competitive, the transportation and handling cost must be minimized. This requires careful selection of the system and optimal design for efficient operation. The materials handling and system economics research addresses these issues. Transportation and handling technologies for CCBs were investigated from technical, environmental and economic points of view. Five technologies were found promising: (1) Pneumatic Trucks, (2) Pressure Differential Rail Cars, (3) Collapsible Intermodal Containers, (4) Cylindrical Intermodal Tanks, and (5) Coal Hopper Cars with Automatic Retractable Tarping. The first two technologies are currently being utilized in transporting by-products from power plants to disposal sites, whereas the next three are either in development or in conceptualization phases. In this research project, engineering design and cost models were developed for the first four technologies. The engineering design models are in the form of spreadsheets and serve the purpose of determining efficient operating schedules and sizing of system components.

  10. Underground seasonal storage of industrial waste heat; Saisonale Speicherung industrieller Abwaerme im Untergrund

    Energy Technology Data Exchange (ETDEWEB)

    Reuss, M.; Mueller, J. [Bayerische Landesanstalt fuer Landtechnik, TU Muenchen-Weihenstephan, Freising (Germany)

    1998-12-31

    The thermal efficiency of subject systems, especially at higher temperatures is influenced by heat and humidity transport underground. Thermal conductivity and specific thermal capacity depend on the humidity content of the soil. A simulation model was developed that describes the coupled heat and humidity transport in the temperature range up to 90 C. This model will be validated in laboratory and field tests and then be used for designing and analysing underground stores. Pilot plants for the storage of industrial waste heat were designed and planned on the basis of this simulation. In both cases these are cogeneration plants whose waste heat was to be used for space heating and as process energy. Both plants have a very high demand of electric energy which is mostly supplied by the cogeneration plant. The waste heat is put into the store during the summer. In the winter heat is supplied by both the store and the cogeneration plant. In both cases the store has a volume of approx. 15,000 cubic metres with 140 and 210 pits located in a depth of 30 and 40 metres. The plants are used to carry out extensive measurements for the validation of simulation models. (orig.) [Deutsch] Die thermische Leistungsfaehigkeit solcher Systeme wird insbesondere im hoeheren Temperaturbereich durch den Waerme- und Feuchtetransport im Untergrund beeinflusst. Sowohl die Waermeleitfaehigkeit als auch die spezifische Waermekapazitaet sind vom Feuchtegehalt des Bodens abhaengig. Es wurde ein Simulationsmodell entwickelt, das den gekoppelten Waerme- und Feuchtetransport im Temperaturbereich bis 90 C beschreibt. Dieses Modell wird an Labor- und Feldexperimenten validiert und dient dann zur Auslegung und Analyse von Erdwaermesonden-Speichern. Basierend auf diesen theoretischen Grundlagenarbeiten wurden Pilotanlagen zur saisonalen Speicherung industrieller Abwaerme ausgelegt und geplant. In beiden Faellen handelt es sich um Kraft/Waermekopplungsanlagen, deren Abwaerme zur Gebaeudeheizung und

  11. Los Alamos National Laboratory environmental restoration program group audit report for underground storage tank removal: Audit ER-92- 04, July 22--August 11, 1992

    International Nuclear Information System (INIS)

    Gillespie, P.F.

    1992-01-01

    Audit ER-92-04 was conducted on activities being performed by Waste Management (EM-7), Environmental Protection (EM-8), and Environmental Restoration (EM-13) groups for the LANL's underground storage tank removal program. Scope of the audit was limited to an evaluation of the implementation of the State of New Mexico requirements for underground storage-tank removal. Activities were evaluated using requirements specified in the State of New Mexico Environmental Improvement Board Underground Storage Tank Regulations, EIB/USTR. Two recommendations are made: (1) that a single organization be given the responsibility and authority for the implementation of the program, and (2) that the requirements of the NM State environmental improvement board underground storage tank regulations be reviewed and a Los Alamos procedure written to address requirements and interfaces not contained in SOP-EM7-D ampersand D-001

  12. Interactions between fluids and natural clay rich sediments: experimental study in conditions simulating radioactive wastes underground storage

    International Nuclear Information System (INIS)

    Roubeuf, V.

    2000-10-01

    The behaviour of clay rich sediments, especially an argilite from Oxfordian of Haute-Marne, a siltite from Albian series of Marcoule (Gard) and a bentonite from Wyoming, were experimentally studied under physical-chemical conditions close of those of an underground radioactive waste storage. The several steps of the creation of the storage in deep formation were simulated experimentally, in particular: - the effect due to oxidation at ambient temperature and moisture degree related to the arrival of air in the gallery, was tested, especially the interaction between acid fluids generated at the micron-scale of the altered pyrite micro-site and the surrounding minerals of the sediment, - the alteration due to weathering (damping/drying cycles) to simulate the effect of a surface storage of the sediments, - and finally, water-rock interactions at 80 and 200 deg C, which reproduce the thermic stress induced by the deposit of type C radioactive containers (stage of re-hydration under thermic stress). The various simulations lead to rather similar behaviour of minerals in the sediment and solutions. Mineralogical, geochemical and crystallographic analyses show that most minerals in sediments are preserved with no evidence of mineral neo-formation. Nevertheless, the study by X-ray diffraction shows variations in the interlayer spacing in relation with modifications of the hydration states. Changes in the interlayer occupancy of the clays are due to cationic exchange of the sodium of the interlayer by the calcium issued from the dissolution of carbonate and gypsum dissolution. I/S like minerals crystal-chemistry generally display little changes in the tetrahedral and octahedral occupancy and a rather good stability of crystal structure. The cationic exchange capacity (CEC) of the clay sediment display un-significant variations: after the damping/drying cycles, the argilite of Haute-Marne has lost about 15 % of their bulk CEC and the effect of acid micro-environment at

  13. Estimation of the proximity of private domestic wells to underground storage tanks: Oklahoma pilot study.

    Science.gov (United States)

    Weaver, James W; Murray, Andrew R; Kremer, Fran V

    2017-12-31

    For protecting drinking water supplies, the locations of areas with reliance on private domestic wells (hereafter referred to as "wells") and their relationship to contaminant sources need to be determined. A key resource in the U.S. was the 1990 Census where the source of domestic drinking water was a survey question. Two methods are developed to update estimates of the areal density of well use using readily accessible data. The first uses well logs reported to the states and the addition of housing units reported to the Census Bureau at the county, census tract and census block group scales. The second uses housing units reported to the Census and an estimated well use fraction. To limit the scope and because of abundant data, Oklahoma was used for a pilot project. The resulting well density estimates were consistent among spatial scales, and were statistically similar. High rates of well use were identified to the north and east of Oklahoma City, primarily in expanding cities located over a productive aquifer. In contrast, low rates of well use were identified in rural areas without public water systems and in Oklahoma's second largest city, Tulsa, each attributable to lack of suitable ground water. High densities of well use may be expected in rural areas without public water systems, expanding cities and suburbs, and legacy areas of well usage. The completeness of reported well logs was tested by counts from neighborhoods with known reliance on wells which showed reporting rates of 20% to 98%. Well densities in these neighborhoods were higher than the larger-scale estimates indicating that locally high densities typically exist within analysis units. A Monte Carlo procedure was used to determine that 27% of underground storage tanks that had at least one well within a typical distance of concern of 300m (1000ft). Published by Elsevier B.V.

  14. Thermal hardening of saturated clays. Application to underground storage of radioactive wastes

    International Nuclear Information System (INIS)

    Picard, Jean-Marc

    1994-01-01

    Saturated clays submitted to constant mechanical loading and slow temperature increase frequently undergo irreversible contractions. This phenomena is described here by means of a change of plastic limits induced by temperature only, called thermal hardening. Constitutive laws adapted to this kind of plastic behaviour can be formulated within a general framework that satisfies thermodynamical principles. It shows that this coupling results from the presence of a latent heat during the isothermal hardening of plastic limits. A thermomechanical extension of Cam Clay model is then proposed and used in the analysis of laboratory thermomechanical tests performed on clay materials. Making use of tests already published, we show the adequacy of the concept of thermal hardening for clay behaviour. Some clay from deep geological formation considered for the disposal of radioactive waste exhibit thermal hardening in laboratory tests. The consequences for the underground storage facilities during the thermal loading created by the waste are investigated by means of in situ tests as well as numerical computation. The measurement around a heating probe buried in the clay mass demonstrate the significance of thermo-hydro-mechanical couplings. An accurate understanding of in situ measurements is achieved by means of numerical modeling in which the interaction between the various loading of the tests (excavation, pore pressure seepage, and heating) is carefully taken into account. Thermal hardening of the clay appears to be of little influence in these in situ tests. On the other hand, the magnitude of thermo-hydro-mechanical couplings observed in situ are higher than might have been expected from laboratory tests. A more accurate prediction is obtained if one takes into account the more stiffer behaviour of clays when they are subjected to small deformations. (authors)

  15. Thermoluminescence response of calcic bentonite subjected to conditions of high nuclear waste underground storage

    International Nuclear Information System (INIS)

    Dies, J.; Miralles, L.; Tarrasa, F.; Pueyo, J.J.; Cuevas, C. de las

    2002-01-01

    Bentonite is regarded as a backfilling material for underground storage facilities of highly radioactive nuclear waste built on granite formations. In these facilities, bentonite will be subjected to a gradient of temperature and dose rate, achieving a very high integrated dose and, therefore, changes in its structure and physical properties may take place. Two experiments to discriminate between the thermal and the irradiation effect were performed. In the first (named BIC-2A), samples were subjected to temperature while in second (named BIC-2B) the combined effect of temperature and irradiation was studied. The experimental conditions were: a thermal gradient between 130 deg. C and 90 deg. C, a maximum dose rate of 3.5 kGy.h -1 and a gradient of the integrated dose between 1.75 MGy and 10 MGy. Both experiments lasted a total of 124 days. An irradiation source of 60 Co with an activity close to 300,000 Ci, and bentonite samples of 200 mm in length and 50 mm in diameter were used. After the experiment, the samples were ground and two fractions were obtained: a fine fraction ( 80 μm). The results are described of thermoluminescence analyses on the two fractions obtained which showed that the coarse fractions can be 100 times more sensitive to radiation than the fine fraction. On the other hand, the heated and irradiated samples showed a thermoluminescence response around 50 times greater than the samples that were only heated. In addition to this, the temperature and dose rate conditions are relevant parameters in the generation and stabilisation of radiation induced defects. Finally, the response of samples heated and irradiated for two months was quite similar to that obtained on samples heated and irradiated for four months, indicating a saturation phenomenon. (author)

  16. Heat transfer modelling in a spent-fuel dry storage system

    International Nuclear Information System (INIS)

    Ritz, J.B.; Le Bonhomme, S.

    2001-01-01

    The purpose of this paper is to present a numerical modelling of heat transfers in a Spent-Fuel horizontal dry storage. The horizontal dry storage is an interesting issue to momentary store spent fuel containers before the final storage. From a thermal point of view, the cooling of spent fuel container by natural convection is a suitable and inexpensive process but it necessitates to well define the dimensions of the concept due to the difficulty to control the thermal environment. (author)

  17. Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

    Energy Technology Data Exchange (ETDEWEB)

    Guenther, R J; Johnson, Jr, A B; Lund, A L; Gilbert, E R [and others

    1996-07-01

    The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl{sub x}, UAl{sub x}-Al and U{sub 3}O{sub 8}-Al cermets, U-5% fissium, UMo, UZrH{sub x}, UErZrH, UO{sub 2}-stainless steel cermet, and U{sub 3}O{sub 8}-stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified.

  18. Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant

    International Nuclear Information System (INIS)

    Guenther, R.J.; Johnson, A.B. Jr.; Lund, A.L.; Gilbert, E.R.

    1994-11-01

    The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl x , UAl x -Al and U 3 O 8 -Al cermets, U-5% fissium, UMo, UZrH x , UErZrH, UO 2 -stainless steel cermet, and U 3 O 8 -stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified

  19. Behaviour of power and research reactor fuel in wet and dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Freire-Canosa, J [Nuclear Waste Management Organization (Canada)

    2012-07-01

    Canada has developed extensive experience in both wet and dry storage of CANDU fuel. Fuel has been stored in water pools at CANDU reactor sites for approximately 45 years, and in dry storage facilities for a large part of the past decade. Currently, Canada has 38 450 t U of spent fuel in storage, of which 8850 t U are in dry storage. In June 2007, the Government of Canada selected the Adaptive Phased Management (APM) approach, recommended by the Nuclear Waste Management Organization (NWMO), for the long-term management of Canada's nuclear-fuel waste. The Canadian utilities and AECL are conducting development work in extended storage systems as well as research on fuel behaviour under storage conditions. Both activities have as ultimate objective to establish a technical basis for assuring the safety of long-term fuel storage.

  20. Report from SG 1.2: use of 3-D seismic data in exploration, production and underground storage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The objective of this study was to investigate the experience gained from using 3D and 4D techniques in exploration, production and underground storage. The use of 3D seismic data is increasing and considerable progress in the application of such data has been achieved in recent years. 3D is now in extensive use in exploration, field and storage development planning and reservoir management. By using 4D (or time-lapse) seismic data from a given producing area, it is also possible to monitor gas movement as a function of time in a gas field or storage. This emerging technique is therefore very useful in reservoir management, in order to obtain increased recovery, higher production, and to reduce the risk of infill wells. These techniques can also be used for monitoring underground gas storage. The study gives recommendations on the use of 3D and 4D seismic in the gas industry. For this purpose, three specific questionnaires were proposed: the first one dedicated to exploration, development and production of gas fields (Production questionnaire), the second one dedicated to gas storages (Storage questionnaire) and the third one dedicated to the servicing companies. The main results are: - The benefit from 3D is clear for both producing and storage operators in improving structural shape, fault pattern and reservoir knowledge. The method usually saves wells and improve gas volume management. - 4D seismic is an emerging technique with high potential benefits for producers. Research in 4D must focus on the integration of seismic methodology and interpretation of results with production measurements in reservoir models. (author)

  1. Transitioning aluminum clad spent fuels from wet to interim dry storage

    International Nuclear Information System (INIS)

    Louthan, M.R. Jr.; Iyer, N.C.; Sindelar, R.L.; Peacock, H.B. Jr.

    1994-01-01

    The United States Department of Energy (DOE) currently owns several hundred metric tons of aluminum clad, spent nuclear fuel and target assemblies. The vast majority of these irradiated assemblies are currently stored in water basins that were designed and operated for short term fuel cooling prior to fuel reprocessing. Recent DOE decisions to severely limit the reprocessing option have significantly lengthened the time of storage, thus increasing the tendency for corrosion induced degradation of the fuel cladding and the underlying core material. The portent of continued corrosion, coupled with the age of existing wet storage facilities and the cost of continuing basin operations, including necessary upgrades to meet current facility standards, may force the DOE to transition these wet stored, aluminum clad spent fuels to interim dry storage. The facilities for interim dry storage have not been developed, partially because fuel storage requirements and specifications for acceptable fuel forms are lacking. In spite of the lack of both facilities and specifications, current plans are to dry store fuels for approximately 40 to 60 years or until firm decisions are developed for final fuel disposition. The transition of the aluminum clad fuels from wet to interim dry storage will require a sequence of drying and canning operations which will include selected fuel preparations such as vacuum drying and conditioning of the storage atmosphere. Laboratory experiments and review of the available literature have demonstrated that successful interim dry storage may also require the use of fuel and canister cleaning or rinsing techniques that preclude, or at least minimize, the potential for the accumulation of chloride and other potentially deleterious ions in the dry storage environment. This paper summarizes an evaluation of the impact of fuel transitioning techniques on the potential for corrosion induced degradation of fuel forms during interim dry storage

  2. Geomechanical problems of an underground storage of spent nuclear fuel and their mathematic modelling

    Czech Academy of Sciences Publication Activity Database

    Blaheta, Radim; Byczanski, Petr; Šňupárek, Richard; Hájek, Antonín

    2007-01-01

    Roč. 12, č. 1 (2007), s. 140-146 ISSN 1335-1788 Institutional research plan: CEZ:AV0Z30860518 Keywords : mathematical modelling * thermo-mechanical processes * underground deposition Subject RIV: BA - General Mathematics

  3. Underground rock storage concepts for natural gas and LPG in Finland

    International Nuclear Information System (INIS)

    Saerkkae, P.

    1990-01-01

    Natural gas storage concepts are developed in Finland for both deep, unlined rock storages and cryogenic lined, near-surface storages. For butane and propane, Neste Oy has two unlined rock storages in Porvoo. Up to now, experiences are good on storage of LPG in rock temperature and higher than hydrostatic pressure. (author). 3 refs, 8 figs

  4. Dry cask storage: a Vepco/DOE/EPRI cooperative demonstration program

    International Nuclear Information System (INIS)

    Smith, M.L.

    1984-01-01

    In response to a Department of Energy (DOE) Solicitation for Cooperative Agreement Proposal, Virginia Electric and Power Company (Vepco) proposed to participate in a spent fuel storage demonstration program utilizing the dry cask storage technology. This proposed program includes dry cask storage at Vepco's Surry Nuclear Power Station and research and development activities at a DOE site in support of the licensed program at Surry. Phase I of Vepco's two-phase program involves a demonstration of the licensed dry cask storage of spent fuel in an inert atmosphere at the Surry Power Station site. Phase II of Vepco's proposed program will involve the demonstration of storing unconsolidated and consolidated spent fuel in dry casks filled only with air. This phase of the program will involve DOE site testing similar to Phase I and is expected to require an additional (fourth) cask to demonstrate storage of unconsolidated spent fuel in air-filled casks

  5. A new framework to assess risk for a spent fuel dry storage facility

    International Nuclear Information System (INIS)

    Ryu, J. H.; Jae, M. S.; Jung, C. W.

    2004-01-01

    A spent fuel dry storage facility is a dry cooling storage facility for storing irradiated nuclear fuel and associated radioactive materials. It has very small possibilities to release radiation materials. It means a safety analysis for a spent fuel dry storage facility is required before construction. In this study, a new framework for assessing risk associated with a spent fuel dry storage facility is represented. A safety assessment framework includes 3 modules such as assessment of basket/cylinder failure rates, that of overall storage system, and site modeling. A reliability physics model for failure rates, event tree analysis(ETA)/fault tree analysis for system analysis, Bayesian analysis for initial events data, and MACCS code for consequence analysis have been used in this study

  6. FY 1999 research and development results. Preparatory study for the underground thermal energy storage system; 1999 nendo chichu jiban chikunetsu system gijutsu sendo kenkyu kaihatsu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-05-01

    The study is conducted for the underground thermal energy storage system which utilizes heat capacity of the underground, e.g., aquifer, to exchange heat with the underground, and the FY 1999 results are described. For establishment of the concept of the underground heat storage systems, 2 sites are selected for each of Tokyo, Osaka and Sapporo for the study as the geological ground models, for their weather characteristics. Two cases are considered for the site where underground heat exchangers are installed, open space and immediately below a building. The heat-storage system comprises a high-efficiency heat pump, water heat-storage tank and cooling tower. The evaluation results indicate that energy saving rate of 37% or more and CO2 reduction rate of 9.5% or more are achievable in all areas except Sapporo, i.e., Tokyo and Osaka. The economic evaluation results indicate that the simple pay-out period is around 100 years for Tokyo and Osaka, and 80 years for Sapporo. The underground heat storage system is approximately 10% lower in life-cycle cost than the conventional system, 3 versus 3.3 billion yen for the period of 60 years. (NEDO)

  7. Drying and storage effects on poly(ethylene glycol) hydrogel mechanical properties and bioactivity.

    Science.gov (United States)

    Luong, P T; Browning, M B; Bixler, R S; Cosgriff-Hernandez, E

    2014-09-01

    Hydrogels based on poly(ethylene glycol) (PEG) are increasingly used in biomedical applications because of their ability to control cell-material interactions by tuning hydrogel physical and biological properties. Evaluation of stability after drying and storage are critical in creating an off-the-shelf biomaterial that functions in vivo according to original specifications. However, there has not been a study that systematically investigates the effects of different drying conditions on hydrogel compositional variables. In the first part of this study, PEG-diacrylate hydrogels underwent common processing procedures (vacuum-drying, lyophilizing, hydrating then vacuum-drying), and the effect of this processing on the mechanical properties and swelling ratios was measured. Significant changes in compressive modulus, tensile modulus, and swelling ratio only occurred for select processed hydrogels. No consistent trends were observed after processing for any of the formulations tested. The effect of storage conditions on cell adhesion and spreading on collagen- and streptococcal collagen-like protein (Scl2-2)-PEG-diacrylamide hydrogels was then evaluated to characterize bioactivity retention after storage. Dry storage conditions preserved bioactivity after 6 weeks of storage; whereas, storage in PBS significantly reduced bioactivity. This loss of bioactivity was attributed to ester hydrolysis of the protein linker, acrylate-PEG-N-hydroxysuccinimide. These studies demonstrate that these processing methods and dry storage conditions may be used to prepare bioactive PEG hydrogel scaffolds with recoverable functionality after storage. © 2013 Wiley Periodicals, Inc.

  8. Loss of selenium in drying and storage of agronomic plant species

    DEFF Research Database (Denmark)

    Nielsen, Gunnar Gissel

    1970-01-01

    In two experiments with Se75, loss of selenium from agricultural species was noted during both drying and storage. The loss of selenium during drying was to some extent overshadowed by the influence of self-absorption caused by the water in the fresh material. The results showed that even plant...... material of non-indicator plantslose volatile selenium at drying temperatures of 60°C or higher, and in some cases even at temperatures below 60°C. The results also showed that storage as briquettes gives the lowest storage loss of selenium....

  9. Development of road hydronic snow-ice melting system with solar energy and seasonal underground thermal energy storage

    Energy Technology Data Exchange (ETDEWEB)

    Gao, Q.; Liu, Y.; Ma, C.Q.; Li, M.; Huang, Y.; Yu, M. [Jilin Univ., Changchun (China). Dept. of Thermal Energy Engineering; Liu, X.B. [Climate Master Inc., OK (United States)

    2008-07-01

    Snow and ice melting technologies that used thermal energy storage were explored. The study included analyses of solar heat slab, seasonal underground thermal energy storage, and embedded pipe technologies. Different road materials, roadbed construction methods, and underground rock and soil conditions were also discussed. New processes combining all 3 of the main technologies were also reviewed. Other thermal ice melting technologies included conductive concrete and asphalt; heating cables, and hydronic melting systems. Geothermal energy is increasingly being considered as a means of melting snow and ice from roads and other infrastructure. Researchers have also been focusing on simulating heat transfer in solar collectors and road-embedded pipes. Demonstration projects in Japan, Switzerland, and Poland are exploring the use of combined geothermal and solar energy processes to remove snow and ice from roads. Research on hydronic melting technologies is also being conducted in the United States. The study demonstrated that snow-ice melting energy storage systems will become an important and sustainable method of snow and ice removal in the future. The technology efficiently uses renewable energy sources, and provides a cost-effective means of replacing or reducing chemical melting agents. 33 refs., 1 fig.

  10. Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Cox, D. H.

    2000-01-01

    The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved

  11. Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    D. H. Cox

    2000-07-01

    The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved.

  12. Vitrification of underground storage tanks: Technology development, regulatory issues, and cost analysis

    International Nuclear Information System (INIS)

    Tixier, J.S.; Corathers, L.A.; Anderson, L.D.

    1992-03-01

    In situ vitrification (ISV), developed by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE), is a thermal treatment process for the remediation of hazardous, radioactive, or mixed waste sites. The process has been broadly patented both domestically and abroad. Since the inception of ISV in 1980, developmental activities have been focused on applications to contaminated soils, and more recently the potential for application to buried wastes and underground structures (tanks). Research performed to date on the more advanced ISV applications (i.e., application to buried wastes and underground tanks) shows that significant technical and economic potential exists for using ISV to treat buried wastes and underground structures containing radionuclides and/or hazardous constituents. Present ISV applications are directed to the treatment of contaminated soils; the likelihood of using ISV to treat underground tanks depends on the resolution of significant technical and institutional issues related to this advanced application. This paper describes the ISV process and summarizes the technical progress of underground tank vitrification (UTV), discusses pertinent regulatory issues facing the use of UTV, and presents the potential cost of UTV relative to other remedial action alternatives

  13. Dry storage of spent nuclear fuel in UAE – Economic aspect

    International Nuclear Information System (INIS)

    Al Saadi, Sara; Yi, Yongsun

    2015-01-01

    Highlights: • Cost analysis of interim storage of spent nuclear fuel in the UAE was performed. • Two scenarios were considered: accelerated transfer of SNF and max. use of fuel pool. • Additional cost by accelerated transfer of SNF to dry storage was not significant. • Multiple regression analysis was applied to the resulting dry storage costs. • Dry storage costs for different cases could be expressed by single equations. - Abstract: Cost analysis of dry storage of spent nuclear fuel (SNF) discharged from Barakah nuclear power plants in the UAE was performed using three variables: average fuel discharge rate (FD), discount rate (d), and cooling time in a spent fuel pool (T cool ). The costs of dry storage as an interim spent fuel storage option in the UAE were estimated and compared between the following two scenarios: Scenario 1 is ‘accelerated transfer of spent fuel to dry storage’ that SNF will be transferred to dry storage facilities as soon as spent fuel has been sufficiently cooled down in a pool for the dry storage; Scenario 2 is defined as ‘maximum use of spent fuel pool’ that SNF will be stored in a pool as long as possible till the amount of stored SNF in the pool reaches the capacity of the pools and, then, to be moved to dry storage. A sensitivity analysis on the costs was performed and multiple regression analysis was applied to the resulting net present values (NPVs) for Scenarios 1 and 2 and ΔNPV that is difference in the net present values between the two scenarios. The results showed that NPVs and ΔNPV could be approximately expressed by single equations with the three variables. Among the three variables, the discount rate had the largest effect on the NPVs of the dry storage costs. However, ΔNPV was turned out to be equally sensitive to the discount rate and cooling period. Over the ranges of the variables, the additional cost for accelerated fuel transfer (Scenario 1) ranged from 86.4 to 212.9 million $. Calculated using

  14. Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site

    International Nuclear Information System (INIS)

    Bohrman, D.E.; Ingram, E.M.

    1993-09-01

    This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7)

  15. Data needs for long-term dry storage of LWR fuel. Interim report

    International Nuclear Information System (INIS)

    Einziger, R.E.; Baldwin, D.L.; Pitman, S.G.

    1998-04-01

    The NRC approved dry storage of spent fuel in an inert environment for a period of 20 years pursuant to 10CFR72. However, at-reactor dry storage of spent LWR fuel may need to be implemented for periods of time significantly longer than the NRC's original 20-year license period, largely due to uncertainty as to the date the US DOE will begin accepting commercial spent fuel. This factor is leading utilities to plan not only for life-of-plant spent-fuel storage during reactor operation but also for the contingency of a lengthy post-shutdown storage. To meet NRC standards, dry storage must (1) maintain subcriticality, (2) prevent release of radioactive material above acceptable limits, (3) ensure that radiation rates and doses do not exceed acceptable limits, and (4) maintain retrievability of the stored radioactive material. In light of these requirements, this study evaluates the potential for storing spent LWR fuel for up to 100 years. It also identifies major uncertainties as well as the data required to eliminate them. Results show that the lower radiation fields and temperatures after 20 years of dry storage promote acceptable fuel behavior and the extension of storage for up to 100 years. Potential changes in the properties of dry storage system components, other than spent-fuel assemblies, must still be evaluated

  16. Effects of drying method, storage period and carbon: nitrogen ratio ...

    African Journals Online (AJOL)

    Taghwo

    2012-12-03

    Dec 3, 2012 ... African Journal of Environmental Science and Technology Vol. 6(12), pp. .... Drying method 2 (method 2) involved air drying field- fresh soil ... then packed in polyethylene bags and stored at -10°C until inorganic N extraction ...

  17. Improvement of hygienic quality and long-term storage of dried red pepper by gamma irradiation

    International Nuclear Information System (INIS)

    Byun, M.W.; Yook, H.S.; Kwon, J.H.; Kim, J.O.

    1996-01-01

    Dried-red pepper, whole and powdered types, was subjected to a storage-study by investigation the effects of packaging methods (polycloth & polyethylene/polycloth, whole dried-red pepper; nylon/polyethylene-lam-inated film, red pepper powder), temperature and gamma irradiation doses (0-10 kGy). After 6 months storage in polyclith sack at ambient temperature, all whole dried-red pepper showed quality deterioration, such as weight change, insect infestation, discoloration and chemical changes, After 2 years storage in combined packaging with polyethylene/polycloth sack of 5-7.5 kGy irradiated whole dried-red pepper at ambient temperature, however, quality deterioration was not observed. Gamma-irradiated red pepper powder (7.5-10kGy) showed a good quality in hygienic, physicochemical and organoleptic evaluation after 2 years of storage at ambient temperature

  18. Evaluation of Corrosion of Aluminum Based Reactor Fuel Cladding Materials During Dry Storage

    International Nuclear Information System (INIS)

    Peacock, H.B. Jr.

    1999-01-01

    This report provides an evaluation of the corrosion behavior of aluminum cladding alloys and aluminum-uranium alloys at conditions relevant to dry storage. The details of the corrosion program are described and the results to date are discussed

  19. Geomechanical problems of an underground storage of spent nuclear fuel and their mathematic modelling

    Directory of Open Access Journals (Sweden)

    Antonín Hájek

    2007-01-01

    Full Text Available The paper is devoted to the use of mathematical modelling for analysis of the thermo-mechanical (T-M processes, which are relevant for the assessment of underground repositories of the spent nuclear fuel. Wes shall discuss mathematical formulation, numerical methods and parallel alghorithms, which are capable to solve large-scale complicated and coupled 3D problems. Particularly, we show an application of the described methods and parallel computer simulations for analysis of model problems concerning the Swedish KBS3 concept of underground repository.

  20. Acceptance criteria for interim dry storage of aluminum-clad fuels

    International Nuclear Information System (INIS)

    Sindelar, R.L.; Peacock, H.B. Jr.; Iyer, N.C.; Louthan, M.R. Jr.

    1994-01-01

    Direct repository disposal of foreign and domestic research reactor fuels owned by the United States Department of Energy is an alternative to reprocessing (together with vitrification of the high level waste and storage in an engineered barrier) for ultimate disposition. Neither the storage systems nor the requirements and specifications for acceptable forms for direct repository disposal have been developed; therefore, an interim storage strategy is needed to safely store these fuels. Dry storage (within identified limits) of the fuels received from wet-basin storage would avoid excessive degradation to assure post-storage handleability, a full range of ultimate disposal options, criticality safety, and provide for maintaining confinement by the fuel/clad system. Dry storage requirements and technologies for US commercial fuels, specifically zircaloy-clad fuels under inert cover gas, are well established. Dry storage requirements and technologies for a system with a design life of 40 years for dry storage of aluminum-clad foreign and domestic research reactor fuels are being developed by various groups within programs sponsored by the DOE

  1. Conceptual design and cost estimation of dry cask storage facility for spent fuel

    International Nuclear Information System (INIS)

    Maki, Yasuro; Hironaga, Michihiko; Kitano, Koichi; Shidahara, Isao; Shiomi, Satoshi; Ohnuma, Hiroshi; Saegusa, Toshiari

    1985-01-01

    In order to propose an optimum storage method of spent fuel, studies on the technical and economical evaluation of various storage methods have been carried out. This report is one of the results of the study and deals with storage facility of dry cask storage. The basic condition of this work conforms to ''Basic Condition for Spent Fuel Storage'' prepared by Project Group of Spent Fuel Dry Storage at July 1984. Concerning the structural system of cask storage facilities, trench structure system and concrete silo system are selected for storage at reactor (AR), and a reinforced concrete structure of simple design and a structure with membrance roof are selected for away from reactor (AFR) storage. The basic thinking of this selection are (1) cask is put charge of safety against to radioactivity and (2) storage facility is simplified. Conceptual designs are made for the selected storage facilities according to the basic condition. Attached facilities of storage yard structure (these are cask handling facility, cask supervising facility, cask maintenance facility, radioactivity control facility, damaged fuel inspection and repack facility, waste management facility) are also designed. Cost estimation of cask storage facility are made on the basis of the conceptual design. (author)

  2. Status of spent fuel dry storage concepts: concerns, issues and developments

    International Nuclear Information System (INIS)

    1985-11-01

    This report is intended to provide the reader with a general understanding of the various dry storage concepts and facilities required to support them. The outstanding technical concerns relative to dry storage installations, as well as, past and planned demonstration programs are briefly described. Such other activities as the development and approval of a design criteria standard is presented. An updated review of the cost of the various concepts are discussed

  3. High Burnup Dry Storage Cask Research and Development Project, Final Test Plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    2014-02-27

    EPRI is leading a project team to develop and implement the first five years of a Test Plan to collect data from a SNF dry storage system containing high burnup fuel.12 The Test Plan defined in this document outlines the data to be collected, and the storage system design, procedures, and licensing necessary to implement the Test Plan.13 The main goals of the proposed test are to provide confirmatory data14 for models, future SNF dry storage cask design, and to support license renewals and new licenses for ISFSIs. To provide data that is most relevant to high burnup fuel in dry storage, the design of the test storage system must mimic real conditions that high burnup SNF experiences during all stages of dry storage: loading, cask drying, inert gas backfilling, and transfer to the ISFSI for multi-year storage.15 Along with other optional modeling, SETs, and SSTs, the data collected in this Test Plan can be used to evaluate the integrity of dry storage systems and the high burnup fuel contained therein over many decades. It should be noted that the Test Plan described in this document discusses essential activities that go beyond the first five years of Test Plan implementation.16 The first five years of the Test Plan include activities up through loading the cask, initiating the data collection, and beginning the long-term storage period at the ISFSI. The Test Plan encompasses the overall project that includes activities that may not be completed until 15 or more years from now, including continued data collection, shipment of the Research Project Cask to a Fuel Examination Facility, opening the cask at the Fuel Examination Facility, and examining the high burnup fuel after the initial storage period.

  4. 30 CFR 57.4262 - Underground transformer stations, combustible liquid storage and dispensing areas, pump rooms...

    Science.gov (United States)

    2010-07-01

    ....4262 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Fire Prevention... provided with fire protection of a type, size, and quantity that can extinguish fires of any class in their...

  5. A review of technology for verification of waste removal from Hanford Underground Storage Tanks (WHC Issue 30)

    International Nuclear Information System (INIS)

    Thunborg, S.

    1994-09-01

    Remediation of waste from Underground Storage Tanks (UST) at the Hanford Waste storage sites will require removal of all waste to a nearly clean condition. Current requirements are 99% clean. In order to meet remediation legal requirements, a means to remotely verify that the waste has been removed to sufficient level is needed. This report discusses the requirements for verification and reviews major technologies available for inclusion in a verification system. The report presents two operational scenarios for verification of residual waste volume. Thickness verification technologies reviewed are Ultrasonic Sensors, Capacitance Type Sensors, Inductive Sensors, Ground Penetrating Radar, and Magnetometers. Of these technologies Inductive (Metal Detectors) and Ground Penetrating Radar appear to be the most suitable for use as waste thickness sensors

  6. Canadian experience with wet and dry fuel storage concepts

    International Nuclear Information System (INIS)

    Mayman, S.A.

    1978-07-01

    Canada has been storing fuel in water-filled pools for 30 years. There have been no significant problems, but until recently little effort has been invested in quantitative assessment of fuel performance under storage conditions. Work is now in progress to provide such information. Storage pools at nuclear generating stations have operated satisfactorily. The Canadian nuclear industry has nevertheless been studying methods for reducing storage costs and/or increasing reliability. Various concepts, using both water and air cooling, have been suggested. One such concept - the air-cooled concrete canister - is presently under test at the Whiteshell Nuclear Research Establishment. (author)

  7. Recent progress of the waste processing and disposal projects within the Underground Storage Tank-Integrated Demonstration

    International Nuclear Information System (INIS)

    Hunt, R.D.; McGinnis, C.P.; Cruse, J.M.

    1994-01-01

    The US Department of Energy (DOE) Office of Environmental Restoration and Waste Remediation has created the Office of Technology Development (OTD) to provide new and improved remediation technologies for the 1 x 10 8 gal of radioactive waste in the underground storage tanks (USTs) at five DOE sites. The OTD established and the Underground Storage Tank-Integrated Demonstration (UST-ID) to perform demonstrations, tests, and evaluations on these new technologies before these processes are transferred to the tank sites for use in full-scale remediation of the USTs. The UST-ID projects are performed by the Characterization and Waste Retrieval Program or the Waste Processing and Disposal Program (WPDP). During FY 1994, the WPDP is funding 12 projects in the areas of supernate processing, sludge processing, nitrate destruction, and final waste forms. The supernate projects are primarily concerned with cesium removal. A mobile evaporator and concentrator for cesium-free supernate is also being demonstrated. The sludge projects are emphasizing sludge dissolution and the evaluation of the TRUEX and diamide solvent extraction processes for transuranic waste streams. One WPDP project is examining both supernate and sludge processes in an effort to develop a system-level plan for handling all UST waste. The other WPDP studies are concerned with nitrate and organic destruction as well as subsequent waste forms. The current status of these WPDP projects is presented

  8. influence of drying temperature and storage duration on fissuring

    African Journals Online (AJOL)

    User

    age duration on the cracking behaviour and head rice yield of a local rice variety - Jasmine 85. ... harvesting, processing and storage. The rice industry ... cm deep which is within the thickness consid- ered as a ..... Tracing fissure information by.

  9. Dry storage of spent fuel elements: interim facility

    International Nuclear Information System (INIS)

    Quihillalt, O.J.

    1993-01-01

    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

  10. Study on effectiveness of continuous solar dryer integrated with desiccant thermal storage for drying cocoa beans

    Directory of Open Access Journals (Sweden)

    Sari Farah Dina

    2015-03-01

    Full Text Available The main objective is to assess effectiveness of continuous solar dryer integrated with desiccant thermal storage for drying cocoa beans. Two type of desiccants were tested, molecular sieve 13× (Na86 [(AlO286·(SiO2106]·264H2O as an adsorbent type and CaCl2 as an absorbent type. The results revealed that during sunshine hours, the maximum temperature within the drying chamber varied from 40 °C to 54 °C. In average, it was 9–12 °C higher than ambient temperature. These temperatures are very suitable for drying cocoa beans. During off-sunshine hours, humidity of air inside the drying chamber was lower than ambient because of the desiccant thermal storage. Drying times for intermittent directs sun drying, solar dryer integrated with adsorbent, and solar dryer integrated with absorbent were 55 h, 41 h, and 30 h, respectively. Specific energy consumptions for direct sun drying, solar dryer integrated with adsorbent, and solar dryer integrated with absorber were 60.4 MJ/kg moist, 18.94 MJ/kg moist, and 13.29 MJ/kg moist, respectively. The main conclusion can be drawn here is that a solar dryer integrated with desiccant thermal storage makes drying using solar energy more effective in term of drying time and specific energy consumption.

  11. Feasibility and economic consequences of retrievable storage of radioactive waste in the deep underground

    International Nuclear Information System (INIS)

    Prij, J.; Heijdra, J.J.

    1995-01-01

    The economic consequences of retrievable storage have been investigated by comparing two extreme options of retrievable storage. In one option the storage facility is kept in operation using minimal backfill of the storage galleries. In the other option the storage facility is completely backfilled, sealed and abandoned. In the second option construction of a new mine will be necessary in case of retrieval. The point in time has been determined when the second option will be cheaper than the first. This has been done for clay, granite and rock salt as host formation, and both for vitrified waste and spent fuel. (authors)

  12. RADIATION SAFETY JUSTIFICATION FOR THE LONG-TERM STORAGE OF GAS CONDENSATE IN THE UNDERGROUND RESERVOURS FORMED BY THE NUCLEAR EXPLOSION TECHNOLOGY

    Directory of Open Access Journals (Sweden)

    I. K. Romanovich

    2010-01-01

    Full Text Available The paper presents approaches to the safety justification of the gas condensate and brine long-term storage in the underground reservoirs formed by the nuclear explosion technology. Gas condensate and brine are the intermediate level liquid radioactive waste containing isotopes: 3Н, 137Cs and 90Sr, in traces - 239Pu, 235U, 241Am.Safety of the gas condensate and brine long-term storage in the underground reservoirs is assessed on the base of the multi-barrier principle implementation, used during radioactive waste disposal. It is shown that the gas condensate and brine long-term storage in the sealed underground reservoirs formed by nuclear explosion technologies in salt domes does not lead to the surface radioactive contamination and population exposure.

  13. Bruce used fuel dry storage project evolution from Pickering to Bruce

    International Nuclear Information System (INIS)

    Young, R.E.

    1996-01-01

    Additional fuel storage capacity is required at Bruce Nuclear Generating Station, which otherwise would soon fill up all its pool storage capacity. The recommended option was to use a dry storage container similar to that at Pickering. The changes made to the Pickering type of container included: fuel to be stored in trays; the container's capacity increased to 600 bundles; the container's lid to be changed to a metal one; the single concrete lid to be changed to a double metal lid system; the container not to be transportable; the container would be dry-loaded. 7 figs

  14. Thermal safety analysis of a dry storage cask for the Korean standard spent fuel - 16159

    International Nuclear Information System (INIS)

    Cha, Jeonghun; Kim, S.N.; Choi, K.W.

    2009-01-01

    A conceptual dry storage facility, which is based on a commercial dry storage facility, was designed for the Korea standard spent nuclear fuel (SNF) and preliminary thermal safety analysis was performed in this study. To perform the preliminary thermal analysis, a thermal analysis method was proposed. The thermal analysis method consists of 2 parts. By using the method, the surface temperature of the storage canister corresponding to the SNF clad temperature was calculated and the adequate air duct area was decided using the calculation result. The initial temperature of the facility was calculated and the fire condition and half air duct blockage were analyzed. (authors)

  15. Bruce used fuel dry storage project evolution from Pickering to Bruce

    Energy Technology Data Exchange (ETDEWEB)

    Young, R E [Ontario Hydro, Tiverton, ON (Canada). Bruce Nuclear Generating Station-A

    1997-12-31

    Additional fuel storage capacity is required at Bruce Nuclear Generating Station, which otherwise would soon fill up all its pool storage capacity. The recommended option was to use a dry storage container similar to that at Pickering. The changes made to the Pickering type of container included: fuel to be stored in trays; the container`s capacity increased to 600 bundles; the container`s lid to be changed to a metal one; the single concrete lid to be changed to a double metal lid system; the container not to be transportable; the container would be dry-loaded. 7 figs.

  16. Onsite dry spent-fuel storage: Becoming more of a reality

    International Nuclear Information System (INIS)

    1994-01-01

    An overview is presented of dry spent-fuel storage facilities operated at nuclear power plant sites in the USA. The experience of the utilities Virginia Power, Carolina Power and Light Company, Duke Power, Public Service Company of Colorado a Baltimore Gas and Electric is outlined. The spent fuel storage procedure using the Sierra Nuclear container system is described. Plans for the construction of additional storage facilities are mentioned. Dry stores are also operated at nuclear power plants that have been shut down. (J.B.). 1 fig

  17. Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

    International Nuclear Information System (INIS)

    Tyacke, M.J.; McConnell, J.W. Jr.; Ayers, A.L. Jr.; O'Connor, S.C.; Jankovich, J.P.

    1996-01-01

    The Idaho National Engineering Laboratory prepared a technical report for the Office of Nuclear Material Safety and Safeguards of the US Nuclear Regulatory Commission, entitled Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety, NUREG/CR-6407. This paper provides the results of that report. It also presents the graded approach for classification of components used in transportation packagings and dry spent fuel storage systems. This approach provides a method for identifying the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements. The general types of transportation packagings and dry storage systems are identified. The methodology used in this paper is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This paper also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems, with a classification category assigned to each component. Several examples concerning the safety importance of components are presented

  18. The mechanism study between 3D Space-time deformation and injection or extraction of gas pressure change, the Hutubi Underground gas storage

    Science.gov (United States)

    Xiaoqiang, W.; Li, J.; Daiqing, L.; Li, C.

    2017-12-01

    The surface deformation of underground gas reservoir with the change of injection pressure is an excellent opportunity to study the load response under the action of tectonic movement and controlled load. This paper mainly focuses on the elastic deformation of underground structure caused by the change of the pressure state of reservoir rock under the condition of the irregular change of pressure in the underground gas storage of Hutubi, the largest underground gas storage in Xinjiang, at the same time, it makes a fine study on the fault activities of reservoir and induced earthquakes along with the equilibrium instability caused by the reservoir. Based on the 34 deformation integrated observation points and 3 GPS continuous observation stations constructed in the underground gas storage area of Hutubi, using modern measurement techniques such as GPS observation, precise leveling survey, flow gravity observation and so on, combined with remote sensing technology such as InSAR, the 3d space-time sequence images of the surface of reservoir area under pressure change were obtained. Combined with gas well pressure, physical parameters and regional seismic geology and geophysical data, the numerical simulation and analysis of internal changes of reservoir were carried out by using elastic and viscoelastic model, the deformation mechanical relationship of reservoir was determined and the storage layer under controlled load was basically determined. This research is financially supported by National Natural Science Foundation of China (Grant No.41474016, 41474051, 41474097)

  19. Decision and systems analysis for underground storage tank waste retrieval systems and tank waste remediation system

    International Nuclear Information System (INIS)

    Bitz, D.A.; Berry, D.L.; Jardine, L.J.

    1994-03-01

    Hanford's underground tanks (USTs) pose one of the most challenging hazardous and radioactive waste problems for the Department of Energy (DOE). Numerous schemes have been proposed for removing the waste from the USTs, but the technology options for doing this are largely unproven. To help assess the options, an Independent Review Group (IRG) was established to conduct a broad review of retrieval systems and the tank waste remediation system. The IRG consisted of the authors of this report

  20. Dry spent fuel storage experience at overseas nuclear stations focus USA

    International Nuclear Information System (INIS)

    Bradley, T. L.; Kumar, S.; Marcelli, D. G.

    1997-01-01

    This paper provides a summary of US dry spent fuel storage experience, including application of this experience outside the United States. Background information on the US nuclear and spent fuel storage industry is provided as a basis for discussing the various types of options and systems available. An overview of technology options is presented, including systems being used and/or considered by the US government and private sector, as well as a discussion of overall system design, licensing and operation. Factors involved in selecting the best available technology option for a specific site or group of sites are presented, along with a typical timeline for project implementation. Cross-geographical use of technologies under different regulatory and technological regimes is also discussed. The paper concludes that dry storage is safe and reliable based on a successful ten year period. The information presented may be considered for use in the development of dry spent fuel storage in Korea and other countries. (author)

  1. Feasibility of underground storage/disposal of noble gas fission products

    International Nuclear Information System (INIS)

    Winar, R.M.; Trevorrow, L.E.; Steindler, M.J.

    1979-08-01

    The quantities of 85 Kr that can be released to the environment from nuclear energy production are to be limited after 1983 by Federal regulations. Although procedures for collecting the 85 Kr released in the nuclear fuel cycle have been developed to the point that they are commercially available, procedures for terminal disposal of the collected gas are still being examined for their feasibility. In this work, the possibilities of underground disposal of 85 Kr by several techniques were evaluated. It was concluded that (1) disposal of 85 Kr as a solution in water or other solvents in deep wells would have the major disadvantages of liquid migration and the requirement of extremely large volumes of solvent; (2) disposal as bubbles entrained in cement grout injected underground presents the uncertainty of gaseous migration through permeable solid grout; (3) disposal by injection into abandoned oil fields would be favored by solubility of krypton in residual hydrocarbons, but has the disadvantages that such fields contain numerous shafts offering avenues of escape and also that the fields may be reworked in the future for their hydrocarbon residues; (4) underground retention of 85 Kr injected as a gas may be promising, given the right lithology, through entrapment in interstices between fine sand grains held together by the interfacial tension of wetted surfaces. 9 figures, 5 tables

  2. Experimental program to determine maximum temperatures for dry storage of spent fuel

    International Nuclear Information System (INIS)

    Knox, C.A.; Gilbert, E.R.; White, G.D.

    1985-02-01

    Although air is used as a cover gas in some dry storage facilities, other facilities use inert cover gases which must be monitored to assure inertness of the atmosphere. Thus qualifying air as a cover gas is attractive for the dry storage of spent fuels. At sufficiently high temperatures, air can react with spent fuel (UO 2 ) at the site of cladding breaches that formed during reactor irradiation or during dry storage. The reaction rate is temperature dependent; hence the rates can be maintained at acceptable levels if temperatures are low. Tests with spent fuel are being conducted at Pacific Northwest Laboratory (PNL) to determine the allowable temperatures for storage of spent fuel in air. Tests performed with nonirradiated UO 2 pellets indicated that moisture, surface condition, gamma radiation, gadolinia content of the fuel pellet, and temperature are important variables. Tests were then initiated on spent fuel to develop design data under simulated dry storage conditions. Tests have been conducted at 200 and 230 0 C on spent fuel in air and 275 0 C in moist nitrogen. The results for nonirradiated UO 2 and published data for irradiated fuel indicate that above 230 0 C, oxidation rates are unacceptably high for extended storage in air. The tests with spent fuel will be continued for approximately three years to enable reliable extrapolations to be made for extended storage in air and inert gases with oxidizing constituents. 6 refs., 6 figs., 3 tabs

  3. Assessment of nitrogen as an atmosphere for dry storage of spent LWR fuel

    International Nuclear Information System (INIS)

    Gilbert, E.R.; Knox, C.A.; White, G.D.

    1985-09-01

    Interim dry storage of spent light-water reactor (LWR) fuel is being developed as a licensed technology in the United States. Because it is anticipated that license agreements will specify dry storage atmospheres, the behavior of spent LWR fuel in a nitrogen atmosphere during dry storage was investigated. In particular, the thermodynamics of reaction of nitrogen compounds (expected to form in the cover gas during dry storage) and residual impurities (such as moisture and oxygen) with Zircaloy cladding and with spent fuel at sites of cladding breaches were examined. The kinetics of reaction were not considered it was assumed that the 20 to 40 years of interim dry storage would be sufficient for reactions to proceed to completion. The primary thermodynamics reactants were found to be NO 2 , N 2 O, H 2 O 2 , and O 2 . The evaluation revealed that the limited inventories of these reactants produced by the source terms in hermetically sealed dry storage systems would be too low to cause significant spent fuel degradation. Furthermore, the oxidation of spent fuel to degrading O/U ratios is unlikely because the oxidation potential in moist nitrogen limits O/U ratios to values less than UO/sub 2.006/ (the equilibrium stoichiometric form in equilibrium with moist nitrogen). Tests were performed with bare spent UO 2 fuel and nonirradiated UO 2 pellets (with no Zircaloy cladding) in a nitrogen atmosphere containing moisture concentrations greater than encountered under dry storage conditions. These tests were performed for at least 1100 h at temperatures as high as 380 0 C, where oxidation reactions proceed in a matter of minutes. No visible degradation was detected, and weight changes were negligible

  4. Dry storage systems with free convection air cooling

    International Nuclear Information System (INIS)

    Kioes, S.R.

    1980-01-01

    Several design principles to remove heat from the spent fuel by free air convection are illustrated and described. The key safety considerations were felt to be: loss of coolant is impossible as the passive system uses air as a coolant; overheating is precluded because as the temperatures of the containers rises the coolant flow rate increases; mass of the storage building provides a large heat sink and therefore a rapid temperature rise is impossible; and lack of any active external support requirements makes the cooling process less likely to equipment or operator failures. An example of this type of storage already exists. The German HTGR is operated with spherical graphite fuel elements which are stored in canister and in storage cells. The concept is a double cooling system with free convection inside the cells and heat exchange via two side walls of the cell to the ambient air in the cooling ducts. Technical description of the TN 1300 cask is also presented

  5. Accelerated storage testing of freeze-dried Pseudomonas ...

    African Journals Online (AJOL)

    Erika-Chris

    Full Length Research Paper ... was possible to compare rate constants of survival for the freeze-dried P. fluorescens ... studying and predicting the survival loss rate of the ... Erlenmeyer flask containing 3000 ml King B medium. ... The strain was grown in 20 L bioreactor (Biolafite) containing 15 L .... fermented banana media.

  6. Basic Considerations for Dry Storage of Spent Nuclear Fuels and Revisited CFD Thermal Analysis on the Concrete Cask

    International Nuclear Information System (INIS)

    Noh, Jae Soo; Park, Younwon; Song, Sub Lee; Kim, Hyeun Min

    2016-01-01

    The integrity of storage facility and also of the spent nuclear fuel itself is considered very important. Storage casks can be located in a designated area on a site or in a designated storage building. A number of different designs for dry storage have been developed and used in different countries. Dry storage system was classified into two categories by IAEA. One is container including cask and silo, the other one is vault. However, there is various way of categorization for dry storage system. Dry silo and cask are usually classified separately, so the dry storage system can be classified into three different types. Furthermore, dry cask storage can be categorized into two types based on the type of the materials, concrete cask and metal cask. In this paper, the design characteristics of dry storage cask are introduced and computational fluid dynamics (CFD) based thermal analysis for concrete cask is revisited. Basic principles for dry storage cask design were described. Based on that, thermal analysis of concrete dry cask was introduced from the study of H. M. Kim et al. From the CFD calculation, the temperature of concrete wall was maintained under the safety criteria. From this fundamental analysis, further investigations are expected. For example, thermal analysis on the metal cask, thermal analysis on horizontally laid spent nuclear fuel assemblies for transportation concerns, and investigations on better performance of natural air circulation in dry cask can be promising candidates

  7. Basic Considerations for Dry Storage of Spent Nuclear Fuels and Revisited CFD Thermal Analysis on the Concrete Cask

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Jae Soo [ACT Co. Ltd., Daejeon (Korea, Republic of); Park, Younwon; Song, Sub Lee [BEES Inc., Daejeon (Korea, Republic of); Kim, Hyeun Min [KAIST, Daejeon (Korea, Republic of)

    2016-10-15

    The integrity of storage facility and also of the spent nuclear fuel itself is considered very important. Storage casks can be located in a designated area on a site or in a designated storage building. A number of different designs for dry storage have been developed and used in different countries. Dry storage system was classified into two categories by IAEA. One is container including cask and silo, the other one is vault. However, there is various way of categorization for dry storage system. Dry silo and cask are usually classified separately, so the dry storage system can be classified into three different types. Furthermore, dry cask storage can be categorized into two types based on the type of the materials, concrete cask and metal cask. In this paper, the design characteristics of dry storage cask are introduced and computational fluid dynamics (CFD) based thermal analysis for concrete cask is revisited. Basic principles for dry storage cask design were described. Based on that, thermal analysis of concrete dry cask was introduced from the study of H. M. Kim et al. From the CFD calculation, the temperature of concrete wall was maintained under the safety criteria. From this fundamental analysis, further investigations are expected. For example, thermal analysis on the metal cask, thermal analysis on horizontally laid spent nuclear fuel assemblies for transportation concerns, and investigations on better performance of natural air circulation in dry cask can be promising candidates.

  8. Conceptual design of an interim dry storage system for the Atucha nuclear power plant spent fuels

    International Nuclear Information System (INIS)

    Nassini, Horacio E.P.; Fuenzalida Troyano, C.S.; Bevilacqua, Arturo M.; Bergallo, Juan E.

    2005-01-01

    The Atucha I nuclear power station, after completing the rearrangement and consolidation of the spent fuels in the two existing interim wet storage pools, will have enough room for the storage of spent fuel from the operation of the reactor till December 2014. If the operation is extended beyond 2014, or if the reactor is decommissioned, it will be necessary to empty both pools and to transfer the spent fuels to a dry storage facility. This paper shows the progress achieved in the conceptual design of a dry storage system for Atucha I spent fuels, which also has to be adequate, without modifications, for the storage of fuels from the second unity of the nuclear power station, Atucha II, that is now under construction. (author) [es

  9. Analyses of expected rod performance during the dry storage of spent fuel

    International Nuclear Information System (INIS)

    Einziger, R.E.

    1982-08-01

    Within the next ten years, a number of utilities will be forced to increase their interim spent-fuel-storage capability or face the loss of full-core reserve. Dry storage is being considered to fill this need. This paper analyzes the fuel-rod-performance data supporting dry storage and discusses areas where there are still outstanding questions. Three storage temperature ranges (T 0 C, 250 0 C 0 C and T > 400 0 C), two atmospheres (inert, unlimited air) and two initial fuel-rod conditions (intact, breached) are considered. It is concluded that a fuel-performance data base exists that indicates that storage below 250 0 C can be accomplished with long-term fuel pellet and cladding stability. At higher temperatures, analytic studies and laboratory experiments are needed especially to extrapolate and interpret the result of demonstration tests. 2 figures, 2 tables

  10. Economic feasibility of pipe storage and underground reservoir storage options for power-to-gas load balancing

    International Nuclear Information System (INIS)

    Budny, Christoph; Madlener, Reinhard; Hilgers, Christoph

    2015-01-01

    Highlights: • Study of cost effectiveness of power-to-gas and storage of H 2 and renewable methane. • NPV analysis and Monte Carlo simulation to address fuel and electricity price risks. • Gas sale is compared with power and gas market arbitrage and balancing market gains. • Power-to-gas for linking the balancing markets for power and gas is not profitable. • Pipe storage is the preferred option for temporal arbitrage and balancing energy. - Abstract: This paper investigates the economic feasibility of power-to-gas (P2G) systems and gas storage options for both hydrogen and renewable methane. The study is based on a techno-economic model in which the net present value (NPV) method and Monte Carlo simulation of risks and price forward curves for the electricity and the gas market are used. We study three investment cases: a Base Case where the gas is directly sold in the market, a Storage & Arbitrage Case where temporal arbitrage opportunities between the electricity and the gas market are exploited, and a Storage & Balancing Case where the balancing markets (secondary reserve market for electricity, external balancing market for natural gas) are addressed. The optimal type and size of different centralized and decentralized storage facilities are determined and compared with each other. In a detailed sensitivity and cost analysis, we identify the key factors which could potentially improve the economic viability of the technological concepts assessed. We find that the P2G system used for bridging the balancing markets for power and gas cannot be operated profitably. For both, temporal arbitrage and balancing energy, pipe storage is preferred. Relatively high feed-in tariffs (100 € MW −1 for hydrogen, 130 € MW −1 for methane) are required to render pipe storage for P2G economically viable

  11. Combined Thermal Management and Power Generation Concept for the Spent Fuel Dry Storage Cask

    International Nuclear Information System (INIS)

    Kim, In Guk; Bang, In Cheol

    2017-01-01

    The management of the spent nuclear fuel generated by nuclear power plants is a major issue in Korea due to insufficient capacity of the wet storage pools. Therefore, it is considered that dry storage system is the one possible solution for storing spent fuel. A dual-purpose metal cask (transportation and storage) is currently developing in Korea. This cask has 21 of fuel assemblies and 16.8 kW of maximum decay heat. To evaluate the critical safety in normal/off normal and accident conditions, critical stabilities were conducted by using CSAS 6.0. The experimental investigation of heat removal of a concrete storage cask was also conducted under normal, off normal and accident conditions. The results of the evaluation showed a good safety of the dry storage cask. The results showed the enhanced thermal performance according to modification of flow rate. To verify combined thermal management and power generation concept, a new type of test facility for dry storage cask was designed in 1/10 scale of concrete dry storage cask. The experimental study involved the cooling methods that are an integrated system on the top of the dry cask and air flow path on the canister wall. The results showed the temperature distribution of the wall and inside of the dry cask at the normal condition. The influence of the change of the heat load and cooling system were investigated. The heat removal by the integrated system is approximately 20% of the total heat removal of the dry cask with reduced wall temperature. In these tests, economic analysis is conducted by applying the concept of the cost and efficiency. Under different decay power cases, the energy efficiency of the heat pipe and Stirling engine are determined and compared based on experimental results. The average efficiencies of the Stirling engine were the range of 2.375 to 3.247% under the power range of 35– 65W. These results showed that advanced dry storage concept had a better cooling performance in comparison with

  12. Critical review of creep FRAPCON-3 model under dry storage conditions

    Energy Technology Data Exchange (ETDEWEB)

    Feria, F.; Herranz, L.E. [Unit of Nuclear Safety Research, CIEMAT, Avda. Complutense 22, Madrid, Madrid 28040 (Spain)

    2009-06-15

    There is a general agreement that cladding creep rupture is the most likely and limiting failure mechanism of spent fuel in dry storage compared to other potential mechanisms, like stress corrosion cracking and/or delayed hydride cracking. Nevertheless, occurrence of creep rupture is very improbable since both decay heat and hoop stress tend to decrease throughout dry storage. In spite of this, the current trend to higher burn up levels needs further attention that ensures safe storage of spent fuel irradiated over 45 GWd/MTU. An extensive work has been carried out during the last four decades in the area of in-reactor creep modelling. Unfortunately, the in-reactor conditions are so different from those prevailing under dry storage, that all the experience gained cannot be extrapolated in a straightforward manner. On the other side, as creep tests simulating conditions throughout a 20-40 year dry storage are impractical, post-irradiation cladding creep behaviour has been modelled by means of time-temperature dependent laws developed on the basis of currently available zirconium alloys data. Additionally, some tests have been exploring the effect of irradiation, hydrogen distribution and material composition on the materials creep behaviour. Adaptation of fuel performance codes initially developed for normal and off-normal reactor operation is not an easy task either. Creep modelling is usually dependent of host codes because a good part of its validation and update has been carried out in an integral way, and as a consequence its independent performance assessment is not an easy task. This work examines the current capability of FRAPCON-3 to model creep behaviour under dry storage conditions. To do so, a review of its major fundamentals has been done and its range of applicability discussed. Once its main approximations and drawbacks have been identified, an attempt to overcome some of them has been intended by implementing an alternative expression for creep under

  13. International and European legal aspects on underground geological storage of CO2

    International Nuclear Information System (INIS)

    Wall, C.; Olvstam, M.-L.; Bernstone, C.

    2005-01-01

    The often disconnected international and European legal rules regarding carbon dioxide (CO 2 ) storage in geological formations create legal uncertainty and a slow down in investments. Existing rules for waste dumping, such as the OSPAR and London Conventions implies that CO 2 storage in sub seabed geological formations is not permitted for climate change mitigating purposes. This paper emphasized that even in cases when complete certainty about the exact application of a legal rule is not possible, it is necessary to know if an activity is lawful. It also emphasized that CO 2 storage should be a priority in the international agenda. The current gaps in knowledge concerning the relevant international and European legislation directly related to CO 2 storage were identified in this paper, including long-term liability for risk of damages caused during the injection phase of the well. The current relevant legislation that is not directly concerned with CO 2 storage but which might have an impact on future legislation was also discussed along with relevant legal principles that might influence future legislation. Some of the many ongoing projects concerning CO 2 storage were reviewed along with papers and reports on regulating CO 2 storage. It was concluded that if CO 2 capture and storage is going to be a large-scale concept for mitigating climate change, the legal issues and requirements need to be an area of priority. 16 refs

  14. Suggestion on the safety classification of spent fuel dry storage in China’s pressurized water reactor nuclear power plant

    Science.gov (United States)

    Liu, Ting; Qu, Yunhuan; Meng, De; Zhang, Qiaoer; Lu, Xinhua

    2018-01-01

    China’s spent fuel storage in the pressurized water reactors(PWR) is stored with wet storage way. With the rapid development of nuclear power industry, China’s NPPs(NPPs) will not be able to meet the problem of the production of spent fuel. Currently the world’s major nuclear power countries use dry storage as a way of spent fuel storage, so in recent years, China study on additional spent fuel dry storage system mainly. Part of the PWR NPP is ready to apply for additional spent fuel dry storage system. It also need to safety classificate to spent fuel dry storage facilities in PWR, but there is no standard for safety classification of spent fuel dry storage facilities in China. Because the storage facilities of the spent fuel dry storage are not part of the NPP, the classification standard of China’s NPPs is not applicable. This paper proposes the safety classification suggestion of the spent fuel dry storage for China’s PWR NPP, through to the study on China’s safety classification principles of PWR NPP in “Classification for the items of pressurized water reactor nuclear power plants (GB/T 17569-2013)”, and safety classification about spent fuel dry storage system in NUREG/CR - 6407 in the United States.

  15. Structural analysis of an underground reinforced concrete waste storage tank due to over-pressurization

    International Nuclear Information System (INIS)

    Xu, J.; Bandyopadhyay, K.; Shteyngart, S.

    1993-01-01

    This paper presents the results of a structural analysis performed by use of the finite element method in determining the pressure-carrying capacity of an underground tank which contains nuclear wastes. The tank and surrounding soil were modeled and analyzed using the ABAQUS program. Special emphasis as given to determining the effects of soil-containment interaction by employing a Coulomb friction model. The effect of material properties was investigated by considering two sets of stress-strain data for the steel plates. In addition, a refined mesh was used to evaluate the strain concentration effects at steel liner thickness discontinuities

  16. Preliminary studies of tunnel interface response modeling using test data from underground storage facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Sobolik, Steven Ronald; Bartel, Lewis Clark

    2010-11-01

    In attempting to detect and map out underground facilities, whether they be large-scale hardened deeply-buried targets (HDBT's) or small-scale tunnels for clandestine border or perimeter crossing, seismic imaging using reflections from the tunnel interface has been seen as one of the better ways to both detect and delineate tunnels from the surface. The large seismic impedance contrast at the tunnel/rock boundary should provide a strong, distinguishable seismic response, but in practice, such strong indicators are often lacking. One explanation for the lack of a good seismic reflection at such a strong contrast boundary is that the damage caused by the tunneling itself creates a zone of altered seismic properties that significantly changes the nature of this boundary. This report examines existing geomechanical data that define the extent of an excavation damage zone around underground tunnels, and the potential impact on rock properties such as P-wave and S-wave velocities. The data presented from this report are associated with sites used for the development of underground repositories for the disposal of radioactive waste; these sites have been excavated in volcanic tuff (Yucca Mountain) and granite (HRL in Sweden, URL in Canada). Using the data from Yucca Mountain, a numerical simulation effort was undertaken to evaluate the effects of the damage zone on seismic responses. Calculations were performed using the parallelized version of the time-domain finitedifference seismic wave propagation code developed in the Geophysics Department at Sandia National Laboratories. From these numerical simulations, the damage zone does not have a significant effect upon the tunnel response, either for a purely elastic case or an anelastic case. However, what was discovered is that the largest responses are not true reflections, but rather reradiated Stoneley waves generated as the air/earth interface of the tunnel. Because of this, data processed in the usual way may not

  17. Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

    International Nuclear Information System (INIS)

    McConnell, J.W., Jr; Ayers, A.L. Jr; Tyacke, M.J.

    1996-02-01

    This report provides a graded approach for classification of components used in transportation packaging and dry spent fuel storage systems. This approach provides a method for identifying, the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements The general types of transportation packagings and dry storage systems were identified. Discussions were held with suppliers and fabricators of packagings and storage systems to determine current practices. The methodology used in this report is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This report also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems. The safety importance of each component is discussed, and a classification category is assigned

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

    Energy Technology Data Exchange (ETDEWEB)

    Saegusa, T [CRIEPI (Japan)

    2012-07-01

    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 UO{sub 2} 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.

  19. Current status on the spent fuel dry storage management in Taiwan

    International Nuclear Information System (INIS)

    Chen, H.T.; Liu, C.H.

    2006-01-01

    Full text: Full text: One of the high priority issues for the continuous operation of nuclear power plants is how to manage and store spent fuel. In recent years, interim dry storage of spent fuel has become a significant solution in extending the storage capacity at a nuclear reactor site that lacks sufficient spent fuel pool storage capacity as in the world, and also in Taiwan. Although the re-racking project for the spent fuel pools has been undertaken, the Taiwan Power Company (TPC) Chinshan nuclear power plant still will lose its full core reserve by the year 2010. TPC has declared to build an on-site interim dry storage facility, this followed by geological disposal represents the most suitable option at this time. TPC is expected to submit the application for construction permit in 2006; preoperational test and storage should be put into operation by the end of 2008. Interim dry storage is a passive system. Materials used play a crucial role in the safety function of cask. The competent authority of spent fuel management in Taiwan, FCMA/AEC, will carry out a confirmatory evaluation regarding heat dissipation, structural seismic analysis, and radiation shielding to assure available safety function for casks after reviewing safety analysis report submitted by TPC. Third party inspection has been required to enhance quality assurance program and foreign technical consultation will be arranged. Although the security level for such facility will be kept to the same level as an NPP, a comprehensive analysis against a commercial airplane attack on cask should be made and addressed in the supplement of SAR. Licensing hearing is also required before issuing the construction permit. The paper presents the review plan and regulatory requirements for the licensing of an interim dry storage of spent fuel, the licensing procedure, and the development of dry storage cask for spent fuel in Taiwan

  20. Economic efficiency of underground natural gas storage: The case of Canada

    International Nuclear Information System (INIS)

    Charette, Y.

    1990-01-01

    The paper describes the current situation of natural gas storage in Canada and attempts to provide valuable information and analytical tools so that the key players, including government and industry, will be in a better position to make enlightened choices for future investments in natural gas storage. Central to the analysis of the efficiency of storage is the notion of efficient peak-load pricing. It is usually recognized that storage may be efficient or welfare increasing because, with fixed consumption, it may allow the substitution of cheaper off-peak production for more costly production. The theoretical conclusions are used of a number of static peak-load pricing models, as well as investment decision models, to analyze the various costs and benefits of storage. The main conclusion is made that, when storage is possible, the welfare maximizing peak/off-peak price differential can be reduced, and therefore, storage can increase the efficiency of the gas transmission system. 10 refs, 2 figs, 5 tabs

  1. Cost comparisons of wet and dry interim storage facilities for PWR spent nuclear fuel in Korea

    International Nuclear Information System (INIS)

    Cho, Chun-Hyung; Kim, Tae-Man; Seong, Ki-Yeoul; Kim, Hyung-Jin; Yoon, Jeong-Hyoun

    2011-01-01

    Research highlights: → We compare the costs of wet and dry interim storage facilities for PWR spent fuel. → We use the parametric method and quotations to deduce unknown cost items. → Net present values and levelized unit prices are calculated for cost comparisons. → A system price is the most decisive factor in cost comparisons. - Abstract: As a part of an effort to determine the ideal storage solution for pressurized water reactor (PWR) spent nuclear fuel, a cost assessment was performed to better quantify the competitiveness of several storage types. Several storage solutions were chosen for comparison, including three dry storage concepts and a wet storage concept. The net present value (NPV) and the levelized unit cost (LUC) of each solution were calculated, taking into consideration established scenarios and facility size. Wet storage was calculated to be the most expensive solution for a 1700 MTU facility, and metal cask storage marked the highest cost for a 5000 MTU facility. Sensitivity analyses on discount rate, metal cask price, operation and maintenance cost, and facility size revealed that the system price is the most decisive factor affecting competitiveness among the storage types.

  2. Cost comparisons of wet and dry interim storage facilities for PWR spent nuclear fuel in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Chun-Hyung, E-mail: skycho@krmc.or.kr [Korea Radioactive Waste Management Corporation, 1045 Daedeokdaero, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of); Kim, Tae-Man; Seong, Ki-Yeoul; Kim, Hyung-Jin; Yoon, Jeong-Hyoun [Korea Radioactive Waste Management Corporation, 1045 Daedeokdaero, Yuseong-Gu, Daejeon 305-353 (Korea, Republic of)

    2011-05-15

    Research highlights: > We compare the costs of wet and dry interim storage facilities for PWR spent fuel. > We use the parametric method and quotations to deduce unknown cost items. > Net present values and levelized unit prices are calculated for cost comparisons. > A system price is the most decisive factor in cost comparisons. - Abstract: As a part of an effort to determine the ideal storage solution for pressurized water reactor (PWR) spent nuclear fuel, a cost assessment was performed to better quantify the competitiveness of several storage types. Several storage solutions were chosen for comparison, including three dry storage concepts and a wet storage concept. The net present value (NPV) and the levelized unit cost (LUC) of each solution were calculated, taking into consideration established scenarios and facility size. Wet storage was calculated to be the most expensive solution for a 1700 MTU facility, and metal cask storage marked the highest cost for a 5000 MTU facility. Sensitivity analyses on discount rate, metal cask price, operation and maintenance cost, and facility size revealed that the system price is the most decisive factor affecting competitiveness among the storage types.

  3. Accessing leaking underground storage tank case studies and publications through the EPA's Computerized On-Line Information System (COLIS)

    International Nuclear Information System (INIS)

    Hillger, R.; Tibay, P.

    1991-01-01

    The US EPA's regulations for underground storage tanks (USTs) require corrective action to be taken in response to leaking USTs. Recent developments of UST programs nationwide as well as the introduction of new technologies to clean up UST sites have increased the diversity of experience levels among personnel involved with this type of work. The EPA's Computerized On-Line Information System (COLIS) has been developed to facilitate technology transfer among the personnel involved in UST cleanup. The system allows for the quick and simple retrieval of data relating to UST incidents, as well as other hazardous waste-related information. The system has been used by response personnel at all levels of government, academia, and private industry. Although it has been in existence for many years, users are just now realizing the potential wealth of information stored in this system. COLIS access can be accomplished via telephone lines utilizing a personal computer and a modem

  4. Development of a computer code to predict a ventilation requirement for an underground radioactive waste storage tank

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Y.J.; Dalpiaz, E.L. [ICF Kaiser Hanford Co., Richland, WA (United States)

    1997-08-01

    Computer code, WTVFE (Waste Tank Ventilation Flow Evaluation), has been developed to evaluate the ventilation requirement for an underground storage tank for radioactive waste. Heat generated by the radioactive waste and mixing pumps in the tank is removed mainly through the ventilation system. The heat removal process by the ventilation system includes the evaporation of water from the waste and the heat transfer by natural convection from the waste surface. Also, a portion of the heat will be removed through the soil and the air circulating through the gap between the primary and secondary tanks. The heat loss caused by evaporation is modeled based on recent evaporation test results by the Westinghouse Hanford Company using a simulated small scale waste tank. Other heat transfer phenomena are evaluated based on well established conduction and convection heat transfer relationships. 10 refs., 3 tabs.

  5. Processing of hazardous material, or damage treatment method for shallow layer underground storage structure

    International Nuclear Information System (INIS)

    Ito, Hiroshi; Sakaguchi, Takehiko; Nishioka, Yoshihiro.

    1997-01-01

    In radioactive waste processing facilities and shallow layer underground structures for processing hazardous materials, sheet piles having freezing pipes at the joint portions are spiked into soils at the periphery of a damaged portion of the shallow layer underground structure for processing or storing hazardous materials. Liquid nitrogen is injected to the freezing pipes to freeze the joint portions of adjacent sheet piles. With such procedures, continuous waterproof walls are formed surrounding the soils at the peripheries of the damaged portion. Further, freezing pipes are disposed in the surrounding soils, and liquid nitrogen is injected to freeze the soils. The frozen soils are removed, and artificial foundation materials are filled in the space except for the peripheries of the damaged portion after the removal thereof, and liquid suspension is filled in the peripheries of the damaged portion, and restoration steps for closing the damaged portion are applied. Then, the peripheries of the damaged portion are buried again. With such procedures, series of treatments for removing contaminated soils and repairing a damaged portion can be conducted efficiently at a low cost. (T.M.)

  6. Novel, low-vibration excavation techniques for underground radioactive waste storage

    International Nuclear Information System (INIS)

    Kogelmann, W.J.

    1994-01-01

    In order to meet the construction specifications of the challenging Yucca Mountain nuclear waste repository, novel, low-vibration tunneling and shaft sinking techniques must be applied. Conventional roadheaders, even with reduced cutting speed, cannot be employed due to the high strength and widely varying physical properties of the rock formations. The Multi Tool Miner (MTM) concept utilizes both an impact hammer, for efficient hard rock mining, and a cutter head, tooled with drag-bits (picks), to profile tunnel walls down to the sound, undisturbed rock, in order to meet the 10,000-year stability requirement for underground structures. As the operational requirements and rock conditions at the Yucca Mountain site are not suitable for wide, transverse open-quotes ripperclose quotes cutting drums, a small diameter, in-line, open-quotes milling augerclose quotes cutter head was developed. The synergetic combination of high-production hammer excavation and precise milling will facilitate the construction of stable, long-life underground structures within the budget limitations mandated by Congress

  7. Creep and shrinkage analysis for concrete spent fuel dry storage module

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, D. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)], E-mail: zhangd@aecl.ca

    2009-07-01

    CANDU reactors are designed in Canada and are built and operated worldwide to produce electricity economically with no emission of green house gases. This paper presents creep and shrinkage analysis for a concrete spent fuel dry storage module of a CANDU nuclear power plant. Creep and shrinkage analysis was performed using a method outlined in American Concrete Institute (ACI) code, and then the creep and shrinkage strains were analyzed in a finite element model to obtain the structural behavior of the concrete module. This demonstrated that the creep and shrinkage analysis for concrete spent fuel dry storage is reasonable. AECL's spent fuel dry storage module is adequate to resist the time-dependent effects due to creep and shrinkage of concrete. (author)

  8. Creep and shrinkage analysis for concrete spent fuel dry storage module

    International Nuclear Information System (INIS)

    Zhang, D.

    2009-01-01

    CANDU reactors are designed in Canada and are built and operated worldwide to produce electricity economically with no emission of green house gases. This paper presents creep and shrinkage analysis for a concrete spent fuel dry storage module of a CANDU nuclear power plant. Creep and shrinkage analysis was performed using a method outlined in American Concrete Institute (ACI) code, and then the creep and shrinkage strains were analyzed in a finite element model to obtain the structural behavior of the concrete module. This demonstrated that the creep and shrinkage analysis for concrete spent fuel dry storage is reasonable. AECL's spent fuel dry storage module is adequate to resist the time-dependent effects due to creep and shrinkage of concrete. (author)

  9. An allowable cladding peak temperature for spent nuclear fuels in interim dry storage

    Science.gov (United States)

    Cha, Hyun-Jin; Jang, Ki-Nam; Kim, Kyu-Tae

    2018-01-01

    Allowable cladding peak temperatures for spent fuel cladding integrity in interim dry storage were investigated, considering hydride reorientation and mechanical property degradation behaviors of unirradiated and neutron irradiated Zr-Nb cladding tubes. Cladding tube specimens were heated up to various temperatures and then cooled down under tensile hoop stresses. Cool-down specimens indicate that higher heat-up temperature and larger tensile hoop stress generated larger radial hydride precipitation and smaller tensile strength and plastic hoop strain. Unirradiated specimens generated relatively larger radial hydride precipitation and plastic strain than did neutron irradiated specimens. Assuming a minimum plastic strain requirement of 5% for cladding integrity maintenance in interim dry storage, it is proposed that a cladding peak temperature during the interim dry storage is to keep below 250 °C if cladding tubes are cooled down to room temperature.

  10. Numerical Simulation of the Thermal Performance of a Dry Storage Cask for Spent Nuclear Fuel

    Directory of Open Access Journals (Sweden)

    Heui-Yung Chang

    2018-01-01

    Full Text Available In this study, the heat flow characteristics and thermal performance of a dry storage cask were investigated via thermal flow experiments and a computational fluid dynamics (CFD simulation. The results indicate that there are many inner circulations in the flow channel of the cask (the channel width is 10 cm. These circulations affect the channel airflow efficiency, which in turn affects the heat dissipation of the dry storage cask. The daily operating temperatures at the top concrete lid and the upper locations of the concrete cask are higher than those permitted by the design specification. The installation of the salt particle collection device has a limited negative effect on the thermal dissipation performance of the dry storage cask.

  11. A study of thermal, structural and shielding safety analysis for dry storage of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Shin, S. H. [Kyungpook Nationl Univ., Daegu (Korea, Republic of)

    1997-03-15

    As a replaced method for MRS, the dry storage has been intensively developed by the advanced countries of nuclear power technology. Currently, the domestic technology for the dry storage is also under development. In the present study, the developed technical standards for USNRC and its operation are summarized. Futhermore, the SAR for VECTRA's NUHOMES satisfied with DOE and NRC's requirements is inversely analyzed and combined with both USNRC's regulatory guide and LLNL's SARS. In the safety analysis of a dry storage, the principal design criteria which identifies the structural and mechanical safety criteria is investigated. Based on the design criteria, hypothetical accident analysis as well as off-normal operation analysis are investigated.

  12. Estimating fault stability and sustainable fluid pressures for underground storage of CO2 in porous rock

    International Nuclear Information System (INIS)

    Streit, J.E.; Hillis, R.R.

    2004-01-01

    Geomechanical modelling of fault stability is an integral part of Australia's GEODISC research program to ensure the safe storage of carbon dioxide in subsurface reservoirs. Storage of CO 2 in deep saline formations or depleted hydrocarbon reservoirs requires estimates of sustainable fluid pressures that will not induce fracturing or create fault permeability that could lead to CO 2 escape. Analyses of fault stability require the determination of fault orientations, ambient pore fluid pressures and in situ stresses in a potential storage site. The calculation of effective stresses that act on faults and reservoir rocks lead then to estimates of fault slip tendency and fluid pressures sustainable during CO 2 storage. These parameters can be visualized on 3D images of fault surfaces or in 2D projections. Faults that are unfavourably oriented for reactivation can be identified from failure plots. In depleted oil and gas fields, modelling of fault and rock stability needs to incorporate changes of the pre-production stresses that were induced by hydrocarbon production and associated pore pressure depletion. Such induced stress changes influence the maximum sustainable formation pressures and CO 2 storage volumes. Hence, determination of in situ stresses and modelling of fault stability are essential prerequisites for the safe engineering of subsurface CO 2 injection and the modelling of storage capacity. (author)

  13. Cost estimation of interim dry storage for Atucha I NPP

    International Nuclear Information System (INIS)

    Bergallo, Juan E.; Fuenzalida Troyano, Carlos S.

    2007-01-01

    A joint effort between NASA and CNEA has been performed in order to evaluate and fix the strategy of interim spent fuel storage for Atucha I nuclear power plant. In this work the cost estimation on the proposed system was performed in order to fix the parameter and design criteria for the next engineering step. The main results achieved show that both alternatives are all in the same range of costs per unit of mass to be stored, the impact on electricity cost is less than 1 US mills/KWh and the scaling factor achieved is 0.85. (author) [es

  14. Facility handling and operational considerations with dry storage casks

    International Nuclear Information System (INIS)

    Moegling, J.; McCreery, P.N.

    1982-09-01

    The Tennessee Valley Authority, in conjunction with US DOE and Pacific Northwest Laboratory, is conducting the first US commercial demonstration of spent fuel storage in casks. The two casks selected for this study are the Castor Ic, on loan from Gesellschaft fur Nuklear Service of Essen, West Germany and the DOE supplied REA 2023, manufactured by Ridihalgh, Eggers, and Associates, of Columbus, Ohio. Preparations began in the spring of 1982. The casks are expected to be loaded with fuel at Brown's Ferry Nuclear Station early in 1984, and the test completed about two years later. NRC is issuing a two-year license for this test under 10 CFR 72

  15. Numerical analysis of temperature and flow effects in a dry, two-dimensional, porous-media reservoir used for compressed air energy storage

    Energy Technology Data Exchange (ETDEWEB)

    Wiles, L.E.

    1979-10-01

    The purpose of the work is to define the hydrodynamic and thermodynamic response of a CAES dry porous media reservoir subjected to simulated air mass cycling. The knowledge gained will provide, or will assist in providing, design guidelines for the efficient and stable operation of the air storage reservoir. The analysis and results obtained by two-dimensional modeling of dry reservoirs are presented. While the fluid/thermal response of the underground system is dependent on many parameters, the two-dimensional model was applied only to those parameters that entered the analysis by virtue of inclusion of the vertical dimension. In particular, the parameters or responses that were quantified or characterized include wellbore heat transfer, heat losses to the vertical boundaries of the porous zone, gravitationally induced flows, producing length of the wellbore, and the effects of nonuniform permeability. The analysis of the wellbore heat transfer included consideration of insulation, preheating (bubble development with heated air), and air mass flow rate.

  16. Practice for dosimetry for a self-contained dry-storage gamma-ray irradiator

    International Nuclear Information System (INIS)

    2002-01-01

    This practice outlines dosimetric procedures to be followed with self-contained dry-storage gamma-ray irradiators. If followed, these procedures will help to ensure that calibration and testing will be carried out with acceptable precision and accuracy and that the samples processed with ionizing radiation from gamma rays in a self-contained dry-storage irradiator receive absorbed doses within a predetermined range. This practice covers dosimetry in the use of dry-storage gamma-ray irradiators, namely self-contained dry storage 137 Cs or 60 Co irradiators (shielded free-standing irradiators). It does not cover underwater pool sources, panoramic gamma-ray sources such as those raised mechanically or pneumatically to irradiate isotropically into a room or through a collimator, nor does it cover self-contained bremsstrahlung x-ray units. The absorbed dose range for the use of the dry-storage self-contained gamma-ray irradiators covered by this practice is typically 1 to 10 5 Gy, depending on the application. The absorbed-dose rate range typically is from 10 -2 to 10 3 Gy/min. This practice describes general procedures applicable to all self-contained dry-storage gamma-ray irradiators. For procedures specific to dosimetry in blood irradiation, see ISO/ ASTM Practice 51939. For procedures specific to dosimetry in radiation research on food and agricultural products, see ISO/ASTM Practice 51900. For procedures specific to radiation hardness testing, see ASTM Practice E 1249. For procedures specific to the dosimetry in the irradiation of insects for sterile release programs, see ISO/ASTM Guide 51940. In those cases covered by ISO/ASTM Practices 51939, 51900, 51940, or ASTM E 1249, those standards take precedence. In addition, this practice does not cover absorbed-dose rate calibrations of radiation protection instrumentation

  17. Storage conditions affect oxidative stability and nutritional composition of freeze-dried Nannochloropsis salina

    DEFF Research Database (Denmark)

    Safafar, Hamed; Langvad, Sten; Møller, Peter

    2017-01-01

    composition of microalgae biomass. In order to investigate the worsening of the nutritional quality of freeze dried biomass, a multifactorial storage experiment was conducted on a high EPA (eicosapentaenoic acid) Nannochloropsis salina biomass. The storage time (0–56 days), storage temperature (5, 20,and 40...... °C and packaging conditions (under vacuum and ambient pressure)used as main factors. During the 56 days of storage, both time and temperature strongly influenced the oxidation reactions which result in deterioration of bioactive compounds such as carotenoids, tocopherols, and EPA. Lipid deterioration......, or cosmetics requires the knowledge of the optimum storage conditions to prevent the value-added compounds from deterioration. Results of this study improve our understanding of the chemical deterioration under different storage conditions and can help the producers/customers to extend the shelf life...

  18. Recent findings on the oxidation of UO2 fuel under nominally dry storage conditions

    International Nuclear Information System (INIS)

    Taylor, P.; McEachern, R.J.; Sunder, S.; Wasywich, K.M.; Miller, N.H.; Wood, D.D.

    1995-01-01

    This paper is an overview of fuel-storage demonstration experiments, supporting research on UO 2 oxidation, and associated model development, in progress at AECL's Whiteshell Laboratories. The work is being performed to determine the time/temperature limits for safe storage of irradiated CANDU fuel in dry air. The most significant recent experimental finding has been the detection of small quantities of U 3 O 8 , formed over periods of one to several years in a variety of experiments at 150-170 deg C. Another important trading is the slight suppression of U 3 O 8 formation in SIMFUEL and other doped U0 2 formulations. The development of a nucleation-and-growth model for U 3 O 8 formation is discussed, along with available activation energy data. These provide a basis for predicting U 3 O 8 formation rates under dry-storage conditions, and hence optimizing fuel storage strategies. (author)

  19. Safety aspects in the dry storage of spent nuclear fuel in long term operation

    Energy Technology Data Exchange (ETDEWEB)

    Nodarim, Claudir J.; Silva, Viviane B. da; Fontes, Gladson S. [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil); Saldanha, Pedro L.C., E-mail: claudirnodari@gmail.com, E-mail: vivisborges@gmail.com, E-mail: gsfontes@hotmail.com, E-mail: Saldanha@cnen.gov.br [Comissão Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The purpose of the present paper is to discuss the safety assessment of the Dry Storage Unit (DSU), taking into account the long term operation and the operational experience already evidenced in similar facilities. In this sense, the RIDM (Risk-Informed Decision-Making) concept will be adopted for the regulatory decision-making process. Potential technical issues associated with the aging of materials from the dry storage unit will be considered. The work will be done using the rules and requirements of 10 CFR Part 72 and the U.S. NRC (United States Nuclear Regulatory Commission) regulatory guides. (author)

  20. Effects of Lower Drying-Storage Temperature on the Ductility of High-Burnup PWR Cladding

    Energy Technology Data Exchange (ETDEWEB)

    Billone, M. C. [Argonne National Lab. (ANL), Argonne, IL (United States); Burtseva, T. A. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-08-30

    The purpose of this research effort is to determine the effects of canister and/or cask drying and storage on radial hydride precipitation in, and potential embrittlement of, high-burnup (HBU) pressurized water reactor (PWR) cladding alloys during cooling for a range of peak drying-storage temperatures (PCT) and hoop stresses. Extensive precipitation of radial hydrides could lower the failure hoop stresses and strains, relative to limits established for as-irradiated cladding from discharged fuel rods stored in pools, at temperatures below the ductile-to-brittle transition temperature (DBTT).

  1. Modeling of dimensional changes of spent WWER fuel rods during dry storage

    International Nuclear Information System (INIS)

    Aliev, T.; Evdokimov, I.; Likhanskii, V.; Sorokin, A.; Kolesnik, M.; Kozhakin, A.; Zborovskii, V.; Zvir, E.; Ilyin, P.

    2015-01-01

    The engineering model of anisotropic creep is developed to predict the behavior of WWER fuel rods in dry storage of spent fuel. The model considers several deformation mechanisms, the main one being the dislocation creep. The effects of radiation defects accumulation and its partial annealing during storage, as well as work hardening are taken into account. Based on the available experimental data preliminary verification of the developed model is performed. The model adequately describes the data set used. Conditions of experiments conducted up to date are more severe in temperature and stresses than ones in dry storage. It is shown that in dry storage additional deformation mechanisms play an important role. One such mechanism is the creep induced by temperature cycling that occurs during the experiments. Thermal cycles produce internal stresses caused by thermal expansion anisotropy in α-Zr crystallites. This mechanism makes a significant contribution to the experimentally measured strain at stresses characteristic for spent fuel claddings. Additional experimental research is planned to expand the range of Verification Matrix to the prototype conditions for dry storage and to improve prediction accuracy of the model. (author)

  2. Assessment of dry storage performance of spent LWR fuel assemblies with increasing burnup

    International Nuclear Information System (INIS)

    Peehs, M.; Garzarolli, F.; Goll, W.

    1999-01-01

    Although the safety of a dry long-term spent fuel store is scarcely influenced if a few fuel rods start to leak during extended storage - since all confinement systems are designed to retain gaseous activity safely - it is a very conservative safety goal to avoid the occurrence of systematic rod defects. To assess the extended storage performance of a spent fuel assembly (FA), the experience can be collated into 3 storage modes: I - fast rate of temperature decrease δ max ≥ δ ≥ 300 deg. C, II - medium rate of decrease for the fuel rod dry storage temperature 300 deg. C > δ ≥ 200 deg. C, III - slow to negligible rate of temperature decrease for δ 2 -fuel are practically immobile during storage. Consequently all fission-product-driven defect mechanisms will not take place. The leading defect mechanism - also for fuel rods with increased burnup - remains creep due to the hoop strain resulting from the fuel rod internal fission gas pressure. Limiting the creep to its primary and secondary stages prevents fuel rod degradation. The allowable uniform strain of the cladding is 1 - 2%. Calculations were performed to predict the dry storage performance of fuel assemblies with a burnup ≤ 55 GW · d/tHM based on the fuel assemblies end of life (EOL)-data and on a representative curve T = f(t). The maximum allowable hot spot temperature of a fuel rod in the CASTOR V cask was between 348 deg. C (U FA) and 358 deg. C (MOX FA). The highest hoop strain predicted after 40 years of storage is 0.77% proving that spent LWR fuel dry storage is safe. (author)

  3. Radioprotection and safety for a dry storage module for bare PWR fuel elements

    International Nuclear Information System (INIS)

    Tzontlimatzin, E.

    1983-01-01

    A module for dry storage of spent fuel from PWR, after a previous cooling time of 2 years, is examined. Biological protection is obtained by 185 cm of concrete. The safety study shows the impossibility of a fast increase in temperature in case of cooling system failure because in this case the module will be cooled by natural convection or thermosiphon. A project for a storage installation consisting of 5 modules for 1500 irradiated fuel assemblies is described [fr

  4. Comparison of Dry Gas Seasonal Storage with CO2 Storage and Re-Use Potential

    OpenAIRE

    Killerud, Marie

    2013-01-01

    To make large-scale CO2 storage economic, many groups have proposed using CO2in EOR projects to create value for CO2 storage. However, CO2 EOR projectsgenerally require a large and variable supply of CO2 and consequently may requiretemporary storage of CO2 in geological formations. In order to store CO2 atoffshore sites as a source for CO2 EOR projects, the CO2 needs to be extractedfrom a storage site to a certain extent. Alternatively, CO2 EOR projects maybe developed alongside saline aquife...

  5. Carbon neutral and flexible underground storage of renewable excess energy; Klimaneutrale Flexibilisierung regenerativer Ueberschussenergie mit Untergrundspeichern

    Energy Technology Data Exchange (ETDEWEB)

    Kuehn, Michael; Nakatem, Natalie; Streibel, Martin; Kempka, Thomas [GeoForschungsZentrum Potsdam (Germany)

    2013-10-15

    We present an innovative, extended and carbon neutral 'Power-to-Gas-to-Power' concept. Excess electricity from wind and sun can be transformed into hydrogen and with carbon dioxide subsequently into methane. When needed, electricity is regained in a combined cycle plant burning the methane. To close the carbon cycle carbon dioxide is captured on site. Two subsurface storage formations for both gases are required for the technology. Our regional showcase of two German cities, Potsdam and Brandenburg/Havel, demonstrates that about 30% of their electricity demand can be provided in that way, using 17.2% of renewable electricity generated in the State of Brandenburg. We calculate the overall efficiency of the system with 27.7% and the associated costs of electricity are 20,43 Euro-cent/ kWh. Compared to pump storage hydro power and compressed air storage the determined efficiency is worse, however the costs of electricity are competitive. (orig.)

  6. Effects of Formation Damage on Productivity of Underground Gas Storage Reservoirs

    Directory of Open Access Journals (Sweden)

    C.I.C. Anyadiegwu

    2013-12-01

    Full Text Available Analysis of the effects of formation damage on the productivity of gas storage reservoirs was performed with depleted oil reservoir (OB-02, located onshore, Niger Delta, Nigeria. Information on the reservoir and the fluids from OB-02 were collected and used to evaluate the deliverabilities of the gas storage reservoir over a 10-year period of operation. The results obtained were used to plot graphs of deliverability against permeability and skin respectively. The graphs revealed that as the permeability decreased, the skin increased, and hence a decrease in deliverability of gas from the reservoir during gas withdrawal. Over the ten years of operating the reservoir for gas storage, the deliverability and permeability which were initially 2.7 MMscf/d and 50 mD, with a skin of 0.2, changed to new values of 0.88 MMscf/d and 24 mD with the skin as 4.1 at the tenth year.

  7. Simulating thermal behavior of AECL's spent fuel dry storage system with CATHENA

    International Nuclear Information System (INIS)

    Sabourin, G.

    1998-01-01

    This paper documents the comparisons between CATHENA predictions and temperature measurements taken at the Gentilly-2 NPP spent fuel dry storage facility and in a mock--up of a storage basket placed inside a storage cylinder. It also presents CATHENA temperature predictions related to the storage of spent fuel in MACSTOR modules as planned for Ignalina NPP, Lithuania. CATHENA has been chosen because it can simulate many noncondensable gases including air and helium, and because of its great flexibility in the representation of the MACSTOR module geometry. The results of the simulations show good agreement with the experimental measurements. The two comparisons indicate that CATHENA can be used to simulate heat transfer from the fuel to the external air circuit of the spent fuel dry storage system. For the Ignalina MACSTOR module, containing RBMK fuel having higher heat release than typical CANDU fuel, CATHENA predicts that the maximum fuel temperature is expected to be around 240 deg C, giving an acceptable margin below the maximum allowed temperature of 300 deg C. In conclusion, this paper shows that the thermalhydraulic code CATHENA can accurately predict the thermal behavior AECL's air cooled spent fuel dry storage system. (author)

  8. Simulating thermal behavior of AECL's spent fuel dry storage system with CATHENA

    Energy Technology Data Exchange (ETDEWEB)

    Sabourin, G. [Atomic Energy of Canada Limited, Montreal, PQ (Canada)

    1998-07-01

    This paper documents the comparisons between CATHENA predictions and temperature measurements taken at the Gentilly-2 NPP spent fuel dry storage facility and in a mock--up of a storage basket placed inside a storage cylinder. It also presents CATHENA temperature predictions related to the storage of spent fuel in MACSTOR modules as planned for Ignalina NPP, Lithuania. CATHENA has been chosen because it can simulate many noncondensable gases including air and helium, and because of its great flexibility in the representation of the MACSTOR module geometry. The results of the simulations show good agreement with the experimental measurements. The two comparisons indicate that CATHENA can be used to simulate heat transfer from the fuel to the external air circuit of the spent fuel dry storage system. For the Ignalina MACSTOR module, containing RBMK fuel having higher heat release than typical CANDU fuel, CATHENA predicts that the maximum fuel temperature is expected to be around 240 deg C, giving an acceptable margin below the maximum allowed temperature of 300 deg C. In conclusion, this paper shows that the thermalhydraulic code CATHENA can accurately predict the thermal behavior AECL's air cooled spent fuel dry storage system. (author)

  9. Underground storage of imported water in the San Gorgonio Pass area, southern California

    Science.gov (United States)

    Bloyd, Richard M.

    1971-01-01

    The San Gorgonio Pass ground-water basin is divided into the Beaumont, Banning, Cabazon, San Timoteo, South Beaumont, Banning Bench, and Singleton storage units. The Beaumont storage unit, centrally located in the agency area, is the largest in volume of the storage units. Estimated long-term average annual precipitation in the San Gorgonio Pass Water Agency drainage area is 332,000 acre-feet, and estimated average annual recoverable water is 24,000 acre-feet, less than 10 percent of the total precipitation. Estimated average annual surface outflow is 1,700 acre-feet, and estimated average annual ground-water recharge is 22,000 acre-feet. Projecting tack to probable steady-state conditions, of the 22.000 acre-feet of recharge, 16,003 acre-feet per year became subsurface outflow into Coachella Valley, 6,000 acre-feet into the Redlands area, and 220 acre-feet into Potrero Canyon. After extensive development, estimated subsurface outflow from the area in 1967 was 6,000 acre-feet into the Redlands area, 220 acre-feet into Potrero Canyon, and 800 acre-feet into the fault systems south of the Banning storage unit, unwatered during construction of a tunnel. Subsurface outflow into Coachella Valley in 1967 is probably less than 50 percent of the steady-state flow. An anticipated 17,000 .acre-feet of water per year will be imported by 1980. Information developed in this study indicates it is technically feasible to store imported water in the eastern part of the Beaumont storage unit without causing waterlogging in the storage area and without losing any significant quantity of stored water.

  10. Extending dry storage of spent LWR fuel for up to 100 years

    International Nuclear Information System (INIS)

    Einziger, R.E.; McKinnon, M.A.; Machiels, A.J.

    1999-01-01

    Because of delays in closing the back end of the fuel cycle in the U.S., there is a need to extend dry inert storage of spent fuel beyond its originally anticipated 20-year duration. Many of the methodologies developed to support initial licensing for 20-year storage should be able to support the longer storage periods envisioned. This paper evaluates the applicability of existing information and methodologies to support dry storage up to 100 years. The thrust of the analysis is the potential behavior of the spent fuel. In the USA, the criteria for dry storage of LWR spent fuel are delineated in 10 CFR 72. The criteria fall into four general categories: maintain subcriticality, prevent the release of radioactive material above acceptable limits, ensure that radiation rates and doses do not exceed acceptable levels, and maintain retrievability of the stored radioactive material. These criteria need to be considered for normal, off-normal, and postulated accident conditions. The initial safety analysis report submitted for licensing evaluated the fuel's ability to meet the requirements for 20 years. It is not the intent to repeat these calculations, but to look at expected behavior over the additional 80 years, during which the temperatures and radiation fields are lower. During the first 20 years, the properties of the components may change because of elevated temperatures, presence of moisture, effects of radiation, etc. During normal storage in an inert atmosphere, there is potential for the cladding mechanical properties to change due to annealing or interaction with cask materials. The emissivity of the cladding could also change due to storage conditions. If there is air leakage into the cask, additional degradation could occur through oxidation in breached rods, which could lead to additional fission gas release and enlargement of cladding breaches. Air in-leakage could also affect cover gas conductivity, cladding oxidation, emissivity changes, and excessive

  11. Extending dry storage of spent LWR fuel for up to 100 years

    International Nuclear Information System (INIS)

    Einziger, R. E.

    1998-01-01

    Because of delays in closing the back end of the fuel cycle in the U.S., there is a need to extend dry inert storage of spent fuel beyond its originally anticipated 20-year duration. Many of the methodologies developed to support initial licensing for 20-year storage should be able to support the longer storage periods envisioned. This paper evaluates the applicability of existing information and methodologies to support dry storage up to 100 years. The thrust of the analysis is the potential behavior of the spent fuel. In the USA, the criteria for dry storage of LWR spent fuel are delineated in 10 CFR 72 [1]. The criteria fall into four general categories: maintain subcriticality, prevent the release of radioactive material above acceptable limits, ensure that radiation rates and doses do not exceed acceptable levels, and maintain retrievability of the stored radioactive material. These criteria need to be considered for normal, off-normal, and postulated accident conditions. The initial safety analysis report submitted for licensing evaluated the fuel's ability to meet the requirements for 20 years. It is not the intent to repeat these calculations, but to look at expected behavior over the additional 80 years, during which the temperatures and radiation fields are lower. During the first 20 years, the properties of the components may change because of elevated temperatures, presence of moisture, effects of radiation, etc. During normal storage in an inert atmosphere, there is potential for the cladding mechanical properties to change due to annealing or interaction with cask materials. The emissivity of the cladding could also change due to storage conditions. If there is air leakage into the cask, additional degradation could occur through oxidation in breached rods, which could lead to additional fission gas release and enlargement of cladding breaches. Air in-leakage could also affect cover gas conductivity, cladding oxidation, emissivity changes, and

  12. Dry storage systems using casks for long term storage in an AFR and repository

    International Nuclear Information System (INIS)

    Einfeld, K.; Popp, F.W.

    1986-01-01

    In conclusion it can be stated that two basic routes with respect to spent fuel storage casks are feasible. One is the Multiple Transport Cask, which with certain modifications can be upgraded to meet the criteria for intermediate storage. Its status is characterized by the licensing of several types of Castor Casks for an intermediate storage period of 30 years in the AFR Storage Facility of DWK at Gorleben in the FRG. The other one is the Final Disposal (Repository) Cask, which can be made suitable for long term storage before a final decision with respect to a repository application is taken. The licensing procedure for a Pilot Conditioning Facility with the Pollux Cask System as reference case will be initiated by DWK in the near future. Under the assumption that in addition to the present Multiple Transport/Storage Casks a license for a Final disposal Cask with respect to long term storage is available, the relative merits of different cask storage systems would have to be evaluated

  13. Hybrid heat pipe based passive cooling device for spent nuclear fuel dry storage cask

    International Nuclear Information System (INIS)

    Jeong, Yeong Shin; Bang, In Cheol

    2016-01-01

    Highlights: • Hybrid heat pipe was presented as a passive cooling device for dry storage cask of SNF. • A method to utilize waste heat from spent fuel was suggested using hybrid heat pipe. • CFD analysis was performed to evaluate the thermal performance of hybrid heat pipe. • Hybrid heat pipe can increase safety margin and storage capacity of the dry storage cask. - Abstract: Conventional dry storage facilities for spent nuclear fuel (SNF) were designed to remove decay heat through the natural convection of air, but this method has limited cooling capacity and a possible re-criticality accident in case of flooding. To enhance the safety and capacity of dry storage cask of SNF, hybrid heat pipe-based passive cooling device was suggested. Heat pipe is an excellent passive heat transfer device using the principles of both conduction and phase change of the working fluid. The heat pipe containing neutron absorber material, the so-called hybrid heat pipe, is expected to prevent the re-criticality accidents of SNF and to increase the safety margin during interim and long term storage period. Moreover, a hybrid heat pipe with thermoelectric module, a Stirling engine and a phase change material tank can be used for utilization of the waste heat as heat-transfer medium. Located at the guide tube or instrumentation tube, hybrid heat pipe can remove decay heat from inside the sealed metal cask to outside, decreasing fuel rod temperature. In this paper, a 2-step analysis was performed using computational fluid dynamics code to evaluate the heat and fluid flow inside a cask, which consisted of a single spent fuel assembly simulation and a full-scope dry cask simulation. For a normal dry storage cask, the maximum fuel temperature is 290.0 °C. With hybrid heat pipe cooling, the temperature decreased to 261.6 °C with application of one hybrid heat pipe per assembly, and to 195.1 °C with the application of five hybrid heat pipes per assembly. Therefore, a dry

  14. The dry spent RBMK fuel cask storage site at the Ignalina NPP in Lithuania

    International Nuclear Information System (INIS)

    Penkov, V.V.; Diersch, R.

    1999-01-01

    At present, there are about 15,000 spent RBMK fuel assemblies stored in the water pools near the reactors at the Ignalina Nuclear Power Plant (INPP). Part of them are cut in two bundles and stored in standardized baskets in the pools. Each basket is loaded with 102 bundles. For long-term interim storage of this fuel, it was decided to use dry storage in casks. For this reason, the total activity to be stored is split into individual units (casks). Each cask represents a closed and independent safety system, fulfilling all safety-relevant requirements for both normal operational and hypothetical accidental conditions. The main safety relevant features of the storage cask system are: (1) Inherent safety system; (2) Double barrier system; (3) Passive cooling by natural convection; (4) Safety against accidents. The cask dry storage system is a cost effective and multi-functional system for storage, transport after the operation time and final disposal under consideration of additional protective elements. From an economical point of view, cask storage has a number of advantages. Two cask types have been intended for the INPP storage site: (1) The CASTOR RBMK cask made of ductile cast iron; (2) The CONSTOR RBMK sandwich cask made of an inner and outer steel shell and reinforced heavy concrete. The CASTOR RBMK and the CONSTOR RBMK casks are designed to withstand severe storage site accidents and with help of impact limiters - to fulfil the IAEA test criteria for type B(U)F packages. The INPP spent RBMK fuel storage site is designed as an open air storage for an operational time of 50 years. The casks are arranged on the concrete storage pad. The site is equipped with a crane for cask handling and technological buildings and security systems. The safety analyses for fuel and cask handling and for cask handling and for cask technology at the site have been made and accepted by the Lithuanian Competent Authority. (author)

  15. Storage mite contamination of commercial dry dog food in south-eastern Australia.

    Science.gov (United States)

    Hibberson, C E; Vogelnest, L J

    2014-06-01

    To evaluate contamination of unopened and opened stored sources of commercial dry dog food by viable storage mites. Prospective laboratory and field study. Samples were collected from nine brands of previously unopened bags (new bags) of dry food and 20 field sources of stored dry food in homes in Sydney and Canberra, Australia. All samples were initially examined for the presence of mites using a stereo-binocular microscope and then placed in separate filter-paper-sealed containers. Field samples were incubated at an average temperature of 29°C and 78% relative humidity (RH) for 5 weeks and then at average 26°C/83% RH for 8 weeks. Paired new-bag samples were stored under room conditions (average 23°C/47% RH) and controlled incubator conditions (average 26°C/80% RH) for 6 weeks. All samples were thoroughly examined for mites, mite eggs and visible mould once weekly using a stereo-binocular microscope. Storage mites were not visualised in any of the field samples or in new-bag samples stored at room temperature. Storage mites, identified as Tyrophagus putrescentiae, were visualised in increasing numbers in seven of nine new-bag samples after incubation, with first mites and then eggs evident after 3 weeks of incubation. We confirmed the presence of viable storage mites in a range of previously unopened commercial dry dog foods in Australia and confirmed the possibility of heavy storage mite contamination for dry food stored under conditions of moderate temperature and high humidity. These findings have relevance to storage mite and/or dust mite sensitivity in canine atopic dermatitis. © 2014 Australian Veterinary Association.

  16. Modelling of seismic reflection data for underground gas storage in the Pečarovci and Dankovci structures - Mura Depression

    Directory of Open Access Journals (Sweden)

    Andrej Gosar

    1995-12-01

    Full Text Available Two antiform structures in the Mura Depression were selected as the most promising in Slovenia for the construction of an underground gas storage facility in an aquifer. Seventeen reflection lines with a total length of 157km were recorded, and three boreholes were drilled. Structural models corresponding to two different horizons (the pre-Tertiary basement and the Badenian-Sarmatianboundary were constructed using the Sierra Mimic program. Evaluation of different velocity data (velocity analysis, sonic log, the down-hole method, and laboratory measurements on cores was carried out in order to perform correct timeto-depth conversion and to estabUsh lateral velocity variations. The porous rock in Pečarovci structure is 70m thick layer of dolomite, occurring at a depth of 1900m, whereas layers of marl, several hundred meter thick, represent the impermeable cap-rock. Due to faults, the Dankovci structure, at a depth of 1200m,where the reservoir rocks consist of thin layers of conglomerate and sandstone,was proved to be less reliable. ID synthetic seismograms were used to correlatethe geological and seismic data at the borehole locations, especially at intervals with thin layers. The raytracing method on 2D models (the Sierra Quik packagewas applied to confirm lateral continuity of some horizons and to improve the interpretation of faults which are the critical factor for gas storage.

  17. Natural drying treatments during seasonal storage of wood for bioenergy in different European locations

    International Nuclear Information System (INIS)

    Roeser, Dominik; Mola-Yudego, Blas; Sikanen, Lauri; Prinz, Robert; Gritten, David; Emer, Beatrice; Vaeaetaeinen, Kari; Erkkilae, Ari

    2011-01-01

    Research into the methods of producing high quality wood chips for a rapidly growing energy sector is becoming increasingly important. For example, small wood chip heating plants require high quality wood chips to ensure efficient operation, thereby minimizing maintenance costs. Moisture content is considered to be an important quality parameter regarding wood based fuels. The objective of this study is to investigate methods to promote the natural drying of wood for bioenergy purposes. The effects on the drying process through covering the wood piles and partial debarking of stems were tested in order to identify methods to reduce the moisture content of the woody material in the storage. Drying trials were established in Finland, Italy and Scotland, utilizing tree species typically used for energy purposes in each area. The results show that natural drying is a viable and effective method to enhance the energy efficiency of wood based fuel products in all the regions studied. Furthermore, by adapting current harvesting methods and storage procedures even better results can be achieved. In addition, the results also indicate that broadleaved trees dry more effectively, if some partial debarking is carried out and that covering of piles is of utmost importance in Scotland and Finland. -- Highlights: → Natural drying is an effective method to enhance efficiency in the wood-fuel chains → Broadleaved trees dry more effectively when partial debarking is done → In Scotland and Finland a method for covering of piles is of utmost importance.

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

    International Nuclear Information System (INIS)

    Wataru, M.; Saegusa, T.; Koga, T.; Sakamoto, K.; Hattori, Y.

    1999-01-01

    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

  19. A new shape design method of salt cavern used as underground gas storage

    International Nuclear Information System (INIS)

    Wang, Tongtao; Yan, Xiangzhen; Yang, Henglin; Yang, Xiujuan; Jiang, Tingting; Zhao, Shuai

    2013-01-01

    Graphical abstract: Safety factor contours of four salt cavern gas storages after running 10 years. Highlights: ► We propose a new model to design the shape of salt cavern gas storage. ► The concepts of slope instability and pressure arch are introduced into the shape design. ► The max. gas pressure determines the shapes and dimensions of cavern lower structure. ► The min. gas pressure decides the shapes and dimensions of cavern upper structure. - Abstract: A new model used to design the shape and dimension of salt cavern gas storage is proposed in the paper. In the new model, the cavern is divided into two parts, namely the lower and upper structures, to design. The concepts of slope instability and pressure arch are introduced into the shape design of the lower and upper structures respectively. Calculating models are established according to the concepts. Field salt cavern gas storage in China is simulated as examples, and its shape and dimension are proposed. The effects of gas pressure, friction angle and cohesion of rock salt on the cavern stability are discussed. Moreover, the volume convergence, displacement, plastic volume rate, safety factor, and effective strain are compared with that of three other existing shapes salt caverns to validate the performance of newly proposed cavern. The results show that the max. gas pressure determines the shape and dimension of cavern lower structure, while the min. gas pressure decides that of cavern upper structure. With the increase of friction angle and cohesion of rock salt, the stability of salt cavern is increased. The newly proposed salt cavern gas storage has more notable advantages than the existing shapes of salt cavern in volume convergence, displacement, plastic volume rate, safety factor, and effective strain under the same conditions

  20. Safeguards-by-Design: Guidance for Independent Spent Fuel Dry Storage Installations (ISFSI)

    Energy Technology Data Exchange (ETDEWEB)

    Trond Bjornard; Philip C. Durst

    2012-05-01

    This document summarizes the requirements and best practices for implementing international nuclear safeguards at independent spent fuel storage installations (ISFSIs), also known as Away-from- Reactor (AFR) storage facilities. These installations may provide wet or dry storage of spent fuel, although the safeguards guidance herein focuses on dry storage facilities. In principle, the safeguards guidance applies to both wet and dry storage. The reason for focusing on dry independent spent fuel storage installations is that this is one of the fastest growing nuclear installations worldwide. Independent spent fuel storage installations are typically outside of the safeguards nuclear material balance area (MBA) of the reactor. They may be located on the reactor site, but are generally considered by the International Atomic Energy Agency (IAEA) and the State Regulator/SSAC to be a separate facility. The need for this guidance is becoming increasingly urgent as more and more nuclear power plants move their spent fuel from resident spent fuel ponds to independent spent fuel storage installations. The safeguards requirements and best practices described herein are also relevant to the design and construction of regional independent spent fuel storage installations that nuclear power plant operators are starting to consider in the absence of a national long-term geological spent fuel repository. The following document has been prepared in support of two of the three foundational pillars for implementing Safeguards-by-Design (SBD). These are: i) defining the relevant safeguards requirements, and ii) defining the best practices for meeting the requirements. This document was prepared with the design of the latest independent dry spent fuel storage installations in mind and was prepared specifically as an aid for designers of commercial nuclear facilities to help them understand the relevant international requirements that follow from a country’s safeguards agreement with

  1. Assessment of the potential of the Mainfranken region, northern Bavaria, for underground storage of geothermal energy; Erkundung des regionalen Potentials fuer die Untergrundspeicherung thermischer Energie in Mainfranken (UTEM)

    Energy Technology Data Exchange (ETDEWEB)

    Barthel, R; Heinrichs, G; Udluft, P [Lehr- und Forschungsbereich Hydrogeologie und Umwelt, Inst. fuer Geologie, Univ. Wuerzburg (Germany); Ebert, H P; Fricke, J [Abt. Waermedaemmung/Waermetransport, Bayerisches Zentrum fuer Angewandte Energieforschung e.V., Wuerzburg (Germany)

    1997-12-01

    The following paper presents a research project that is planned as a cooperation of the Geological Institute, University of Wuerzburg and the Bavarian Center of Applied Energy Research. In this project the potentials for underground thermal energy storage will be investigated in the region of Mainfranken, Northern Bavaria (Main = the river `Main`, Franken = Franconia). All aspects of underground storage will be studied with respect to the specific geographical and geological situation of the area. The study will provide a detailed map of possible storage sites, from which several case studies and at least one demonstration projects will result. (orig.) [Deutsch] Im vorliegenden Beitrag wird ein Forschungsprojekt vorgestellt, das gemeinsam vom Institut fuer Geologie der Universitaet Wuerzburg und dem Zentrum fuer Angewandte Energieforschung in Bayern geplant wird. Ziel des Projekts ist die Erkundung des Potentials fuer die Untergrundspeicherung thermischer Energie in Mainfranken (Nordbayern). Alle Aspekte der Untergrundspeicherung werden regionalspezifisch betrachtet. Neben der Erstellung differenzierter Karten geeigneter Standorte sind Fallstudien und Demonstrationsprojekte in Planung. (orig.)

  2. Technical Aspects Regarding the Preservation of Dry Onions in Different Storage Conditions

    Directory of Open Access Journals (Sweden)

    Marian Vintila

    2014-11-01

    Full Text Available Research refers to the ability to maintain the quality of dry onions in different conditions of temperature, the three varieties used in experimentation (De Buzau, Daytona and Countach being stored after proper preparation at ambient temperature (+20…+22°C, refrigerated (+10…+12°C and cold conditions (+3…+5°C. Storage life, the level of weight (mass and decay losses and evolution of some chemical components determined from the 9 variants led to the conclusion that the best results were obtained by De Buzau variety for storage under ambient conditions and Daytona variety for storage under refrigerated and cold conditions. Moreover large differences between varieties and their behavior depending on storage conditions require choosing resistant cultivars and optimum storage temperatures according to destination and period of marketing or consumption.

  3. Effect of storage time on microbial quality of some spices and dried ...

    African Journals Online (AJOL)

    The effect of storage time on the microbial quality of some spices and dried seasonings (SDS) (dawadawa, pepper, ginger, shrimp and fish powders) was studied over a 12-month period. Microbial load and profile of irradiated and unirradiated SDS were assessed at 0, 6 and 12-month periods. The range of total variable ...

  4. Evaluation of limiting mechanisms for long-term spent fuel dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Rashid, J. [ANATECH Research Corp., San Diego, CA (United States); Machiels, A. [EPRI, Palo Alto, CA (United States)

    2001-07-01

    Several failure mechanisms have been postulated that could become limiting for spent fuel in dry storage. These are: stress Corrosion Cracking (SCC), Delayed Hydride Cracking (DHC) and Creep Rupture (CR). These mechanisms are examined in some detail from two perspectives: their initial environments in which they were developed and applied, and in relation to their applicability to dry storage. Extrapolation techniques are used to transfer the mechanisms from their initial in-reactor and laboratory domains to out-of-reactor spent fuel dry storage environments. This transfer is accomplished both qualitatively where necessary and quantitatively when possible, with fracture toughness used as the transfer function. In this regard, the paper provides useful information on cladding fracture toughness estimates that recognize the specific physical conditions of the cladding, which would not be found elsewhere in the literature. The arguments presented in this paper confirm the general technical consensus that creep is the governing mechanism for spent fuel in long-term dry storage. (author)

  5. Tutorial review of spent-fuel degradation mechanisms under dry-storage conditions

    International Nuclear Information System (INIS)

    Einziger, R.E.

    1983-02-01

    This tutorial reviews our present understanding of fuel-rod degradation over a range of possible dry-storage environments. Three areas are covered: (1) why study fuel-rod degradation; (2) cladding-degradation mechanisms; and (3) the status of fuel-oxidation studies

  6. 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.

  7. Evaluation of limiting mechanisms for long-term spent fuel dry storage

    International Nuclear Information System (INIS)

    Rashid, J.; Machiels, A.

    2001-01-01

    Several failure mechanisms have been postulated that could become limiting for spent fuel in dry storage. These are: stress Corrosion Cracking (SCC), Delayed Hydride Cracking (DHC) and Creep Rupture (CR). These mechanisms are examined in some detail from two perspectives: their initial environments in which they were developed and applied, and in relation to their applicability to dry storage. Extrapolation techniques are used to transfer the mechanisms from their initial in-reactor and laboratory domains to out-of-reactor spent fuel dry storage environments. This transfer is accomplished both qualitatively where necessary and quantitatively when possible, with fracture toughness used as the transfer function. In this regard, the paper provides useful information on cladding fracture toughness estimates that recognize the specific physical conditions of the cladding, which would not be found elsewhere in the literature. The arguments presented in this paper confirm the general technical consensus that creep is the governing mechanism for spent fuel in long-term dry storage. (author)

  8. Structural evaluations of existing underground reinforced concrete tanks for radioactive waste storage

    International Nuclear Information System (INIS)

    Vollert, F.R.

    1979-10-01

    Structural integrity evaluations are being conducted for underground, steel-lined reinforced concrete tanks for storing radioactive wastes. The tanks sustain large soil overburden loads and elevated temperatures from the waste for long time periods. The evaluations include laboratory experiments to determine the long-term effects of elevated temperatures on the elastic properties of concrete, and to estimate the effect of the waste chemicals on concrete durability. Available concrete samples from the tanks were also tested to determine the quality of the concrete in the tanks and for comparison with the laboratory data. Finite element, nonlinear, time-dependent analyses are performed to show the thermal creep, cracking, and stresses occurring in the concrete tanks due to the service conditions. Ultimate load analyses are made to assess the safety margin in the tanks. Finally, seismic analyses of a tank in the stressed condition due to the soil and thermal loadings were conducted to determine that the structure has sufficient reserve capacity to withstand 0.25 g earthquake accelerations

  9. Underground storage tank integrated demonstration: Evaluation of pretreatment options for Hanford tank wastes

    International Nuclear Information System (INIS)

    Lumetta, G.J.; Wagner, M.J.; Colton, N.G.; Jones, E.O.

    1993-06-01

    Separation science plays a central role inn the pretreatment and disposal of nuclear wastes. The potential benefits of applying chemical separations in the pretreatment of the radioactive wastes stored at the various US Department of Energy sites cover both economic and environmental incentives. This is especially true at the Hanford Site, where the huge volume (>60 Mgal) of radioactive wastes stored in underground tanks could be partitioned into a very small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). The cost associated with vitrifying and disposing of just the HLW fraction in a geologic repository would be much less than those associated with vitrifying and disposing of all the wastes directly. Futhermore, the quality of the LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. In this report, we present the results of an evaluation of the pretreatment options for sludge taken from two different single-shell tanks at the Hanford Site-Tanks 241-B-110 and 241-U-110 (referred to as B-110 and U-110, respectively). The pretreatment options examined for these wastes included (1) leaching of transuranic (TRU) elements from the sludge, and (2) dissolution of the sludge followed by extraction of TRUs and 90 Sr. In addition, the TRU leaching approach was examined for a third tank waste type, neutralized cladding removal waste

  10. MICROBIOLOGICAL QUALITY ASSESSMENT OF DRIED YAM CHIPS (Dioscorea rotundata DURING STORAGE

    Directory of Open Access Journals (Sweden)

    Patricia F. Omojasola

    2013-12-01

    Full Text Available Microbiological and physico-chemical analyses of dried yam chips (gbodo retailed in four markets in Ilorin and its environs alongside a laboratory – prepared control were carried out over a six month period. Microbiological assay consisted of total viable and coliform counts as well as microbial isolation. A total of 11 fungi and 5 bacteria were isolated from the different samples which included Acremonium sp., Aspergillus fumigatus., A. niger, A. ochraceus, Fusarium solani, Mucor hiemalis, Mucor racemosus, Penicillum notatum, Rhizopus oryzae, Rhizopus stolonifer, Syncephalastrum racemosum and Bacillus cereus, Bacillus subtilis, Erwinia carotovora, Escherichia coli and Staphylococcus aureus respectively. Total Viable Counts ranged from 3.0-120.0 cfu g-1 and coliform counts ranged from 0.00 - 18.80 cfu g-1 pre-storage to 0.10-219 cfu g-1 and 0.0-31.0 cfu g-1 post storage respectively. The physico-chemical parameters analysed were moisture content which ranged between 14.38-17.10% pre-storage to 13.43-24.96% post-storage; crude protein: 5.81-7.53% and 2.11-6.75%; crude fat: 0.35-0.71% and 0.07-0.61%; ash content: 3.30-5.18% and 1.17-4.77%; crude fibre: 0.77-1.45%; carbohydrate: 70.18-74.00% and 70.93-75.17% pre-storage and post-storage content respectively. Levels of Aflatoxin B1 were also monitored throughout the storage period. Insect infestation of the samples occurred during the storage period. Four species were identified; these were Tribolium casteneum, Dinoderus porcellus, Rhyzopertha dominica and Sitophilus zeamais. The traditional practice of open air sun-drying of yam chips should be discouraged, rather oven drying is recommended to minmize microbial contamination. In addition, sorting to exclude extreneous material and minimize mouldiness and insect infestation is suggested.

  11. The underground as a storage facility. Modelling of nuclear waste repositories and aquifer thermal energy stores

    International Nuclear Information System (INIS)

    Probert, T.

    1998-06-01

    This thesis, which consists of eleven papers and reports, deals with nuclear waste repositories in solid rock and with aquifer thermal energy storage systems. All these storage systems induce multidimensional, time-variable thermo-hydro-elastic processes in the ground in and around the storage region. The partial differential equations that govern the physical processes are solved analytically in some cases, and in other cases numerical models are developed. Many methods of classical mathematical physics are employed for the solution. The analytical approach provides a deeper physical understanding of the processes and their interactions. At large depths, the salinity of groundwater, and hence its density, often increases downwards. In the first study, the upward buoyancy flow of groundwater in fracture planes due to heat release from the nuclear waste is studied considering the added effect of a salt gradient. The aim of the study is to determine the natural barrier effect caused by the salt. A simple formula for the largest upward displacement from the repository is derived. There may be a strong natural barrier, which is independent of fracture permeabilities. In two papers, the temperature field in rock due to a large rectangular grid of heat-releasing canisters containing nuclear waste is studied. The solution is by superposition divided into different parts. There is a global temperature field due to the large rectangular canister area, while a local field accounts for the remaining heat source problem. A complete analytical solution is presented. In the next set of papers, the thermoelastic response from the rectangular field of nuclear waste is analysed. Another study concerns the use of heat as a tracer to investigate flow in a fracture plane. Two papers deal with the thermohydraulic evaluations of two aquifer thermal energy storage projects in southern Sweden. Both plants have been successfully simulated using models based on conformal flow and entropy

  12. Study of blasting seismic effects of underground powerhouse of pumped storage project in granite condition

    Science.gov (United States)

    Wan, Sheng; Li, Hui

    2018-03-01

    Though the test of blasting vibration, the blasting seismic wave propagation laws in southern granite pumped storage power project are studied. Attenuation coefficient of seismic wave and factors coefficient are acquired by the method of least squares regression analysis according to Sadaovsky empirical formula, and the empirical formula of seismic wave is obtained. This paper mainly discusses on the test of blasting vibration and the procedure of calculation. Our practice might as well serve as a reference for similar projects to come.

  13. Analysis of an underground electric heating system with short-term energy storage

    Energy Technology Data Exchange (ETDEWEB)

    Ramadan, B.H. [Michigan State Univ., East Lansing, MI (United States). Dept. of Mechanical Engineering

    1994-12-31

    The principal commercially active heat storage application in which concrete is used as the storage medium is in the use of subfloor electric heaters embedded in a layer of sand. The resistance heaters are energized when utility offpeak rates are in effect. The sand bed and the concrete floor are then heated to some predetermined temperature, and the floor releases heat slowly and remains warm during the subsequent period of high demand. Analysis of the slab-heating system for varying design parameters, such as the depth of the placement of the heaters, the sand properties, the energy input, and the insulation thickness, was considered. The system was also optimized based on life-cycle costs. The suitability of using this system for heating a warehouse in four representative cities in the United States was also considered The response of the system was found to be greatly influenced by the depth of the placement of the heaters, the sand`s moisture content, and the heating strategy. Optimum insulation levels were determined for the prototypical building in all four of the representative cities. Because of the difficulty of controlling the energy release from the heating mats, this system may not be suitable for heating residential and office buildings but may be more appropriate for heating maintenance and storage facilities.

  14. Status analysis for the confinement monitoring technology of PWR spent nuclear fuel dry storage system

    Energy Technology Data Exchange (ETDEWEB)

    Baeg, Chang Yeal; Cho, Chun Hyung [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-03-15

    Leading national R and D project to design a PWR spent nuclear fuel interim dry storage system that has been under development since mid-2009, which consists of a dual purpose metal cask and concrete storage cask. To ensure the safe operation of dry storage systems in foreign countries, major confinement monitoring techniques currently consist of pressure and temperature measurement. In the case of a dual purpose metal cask, a pressure sensor is installed in the interspace of bolted double lid(primary and secondary lid) in order to measure pressure. A concrete storage cask is a canister based system made of double/redundant welded lid to ensure confinement integrity. For this reason, confinement monitoring method is real time temperature measurement by thermocouple placed in the air flow(air intake and exit) of the concrete structure(over pack and module). The use of various monitoring technologies and operating experiences for the interim dry storage system over the last decades in foreign countries were analyzed. On the basis of the analysis above, development of the confinement monitoring technology that can be used optimally in our system will be available in the near future.

  15. CFD Simulation of Heat and Fluid Flow for Spent Fuel in a Dry Storage

    International Nuclear Information System (INIS)

    In, Wangkee; Kwack, Youngkyun; Kook, Donghak; Koo, Yanghyun

    2014-01-01

    A dry storage system is used for the interim storage of spent fuel prior to permanent depository and/or recycling. The spent fuel is initially stored in a water pool for more than 5 years at least after dispatch from the reactor core and is transported to dry storage. The dry cask contains a multiple number of spent fuel assemblies, which are cooled down in the spent fuel pool. The dry cask is usually filled up with helium gas for increasing the heat transfer to the environment outside the cask. The dry storage system has been used for more than a decade in United States of America (USA) and the European Union (EU). Korea is also developing a dry storage system since its spent fuel pool is anticipated to be full within 10 years. The spent fuel will be stored in a dry cask for more than 40 years. The integrity and safety of spent fuel are important for long-term dry storage. The long-term storage will experience the degradation of spent fuel such as the embrittlement of fuel cladding, thermal creep and hydride reorientation. High burn-up fuel may expedite the material degradation. It is known that the cladding temperature has a strong influence on the material degradation. Hence, it is necessary to accurately predict the local distribution of the cladding temperature using the Computational Fluid Dynamics (CFD) approach. The objective of this study is to apply the CFD method for predicting the three-dimensional distribution of fuel temperature in a dry cask. This CFD study simulated the dry cask for containing the 21 fuel assemblies under development in Korea. This paper presents the fluid velocity and temperature distribution as well as the fuel temperature. A two-step CFD approach was applied to simulate the heat and fluid flow in a dry storage of 21 spent fuel assemblies. The first CFD analysis predicted the helium flow and temperature in a dry cask by a assuming porous body of the spent fuel. The second CFD analysis was to simulate a spent fuel assembly in the

  16. Storage properties of gamma-irradiated semi-dried fish varieties

    International Nuclear Information System (INIS)

    Vinh, P.Q.; Alur, M.D.; Nair, P.M.

    1993-01-01

    Several varieties of semi-dried unirradiated and irradiated (1 and 3 kGy) fish, namely, anchovies (Stolephorus commersonii), Bombay duck (Harpodon nehereus), shrimp (Penaeus indicus) and Vietnam scad (Alepes mate) were stored at ambient temperature (26 degree C). During the course of storage, quality characteristics such as total bacterial count (TBC), mould count and biochemical indices of freshness were studied. These studies indicated that initial TBC of semi-dried fish varied from 700-5400 cfu per g of fish, while mould could ranged from 27-1500 cfu per g. However, upon irradiation at 3 kGy, initial bacterial load was considerably reduced. Vietnam scad was not contaminated with mould after 3-5 months of storage at room temperature. Indices such as TVA and TVBN increased during storage at room temperature for both unirradiated and irradiated samples

  17. Safety Test Report for the PWR S/F Dry Storage System

    Energy Technology Data Exchange (ETDEWEB)

    Seo, K. S.; Lee, J. H.; Koo, K. H.; Lee, J. C.; Choi, W. S.; Bang, K. S.; Park, H. Y.; Jang, S. Y

    2008-10-15

    This is contract report conducted by KAERI under the contract with NETEC for safety test for the PWR S/F dry storage system. Leak Test was performed after drop test and turn-over test, the measured leakage rate was lower than allowable leakage rate. It is revealed that the containment integrity of the dry storage system is maintained. In the seismic test, the moving of the model was measured at SRTH seismic response of 0.4 g and 0.8 g. Therefore the seismic test results can be used fully to the test data for verification of the seismic analysis. In the thermal test, the direction of the inlet and outlet of the air has no effect on the heat transfer performance. The passive heat removal system of the horizontal storage module was designed well.

  18. Changes in polyphenol profile of dried apricots containing SO2 at various concentrations during storage.

    Science.gov (United States)

    Altındağ, Melek; Türkyılmaz, Meltem; Özkan, Mehmet

    2018-05-01

    Changes in polyphenols have important effects on the quality (especially color) and health benefits of dried apricots. SO 2 concentration, storage and the activities of polyphenol oxidase (PPO) and phenylalanine ammonia lyase (PAL) were factors which had significant effects on polyphenols. Polyphenol profile and activities of PPO and PAL in sulfured dried apricots (SDAs, 0, 451, 832, 2112 and 3241 mg SO 2 kg -1 ) were monitored during storage at 4, 20 and 30 °C for 379 days for the first time. Even the lowest SO 2 concentration (451 mg kg -1 ) was sufficient to inactivate PPO during the entire storage period. However, while SO 2 led to the increase in PAL activity of the samples (r = 0.767) before storage, PAL activities of SDAs decreased during storage. After 90 days of storage, PAL activity was determined in only non-sulfured dried apricots (NSDAs) and dried apricots containing 451 mg SO 2 kg -1 . Although the major polyphenol in NSDAs was epicatechin (611.4 mg kg -1 ), that in SDAs was chlorogenic acid (455-1508 mg kg -1 ), followed by epicatechin (0-426.8 mg kg -1 ), rutin (148.9-477.3 mg kg -1 ), ferulic acid (23.3-55.3 mg kg -1 ) and gallic acid (2.4-43.6 mg kg -1 ). After storage at 30 °C for 379 days, the major polyphenol in SDAs was gallic acid (706-2324 mg kg -1 ). However, the major polyphenol in NSDAs did not change after storage. The highest total polyphenol content was detected in SDAs containing 2112 mg SO 2 kg -1 and stored at 30 °C. To produce dried apricots having high polyphenol content, ∼2000 mg SO 2 kg -1 should be used. Low storage temperature (<30 °C) was not necessary for the protection of polyphenols. © 2017 Society of Chemical Industry. © 2017 Society of Chemical Industry.

  19. Removal of CO2 by storage in the deep underground, chemical utilization and biofixation. Options for the Netherlands

    International Nuclear Information System (INIS)

    Over, J.A.; De Vries, J.E.; Stork, J.

    1999-07-01

    The Utrecht University in Utrecht, Netherlands, initially put the subject of CO2-storage on the agenda as a possible necessary policy element. During 1990/1991 a number of research institutes and engineering consultants carried out several studies. Also in 1991 the lEA Greenhouse Gas Group (IEA GHG) was initiated, including participation from The Netherlands. The Netherlands Agency for Energy and the Environment (Novem) and the Dutch Ministry of Economic Affairs both attended the meetings of the Executive Committee (ExCo) from the start. This Group started paying attention to the subject of CO2-capturing at large point sources (electricity stations). They then went subsequently from capturing from other (smaller and/or more diffuse) sources, ranking relative to other large scale options to combat or reduce CO2-emissions (i.e. vast areas of forest) to influence and controlling other 'greenhouse gases' such as methane. During 1992/1993 Novem prepared - on request of the Ministry of Economic Affairs - research proposals for investigations and demonstration projects, having a 10 to 15 year horizon, with regard to CO2-capturing technologies. In the beginning of 1994, the Dutch Ministry of Environment (VROM) put more emphasis on demonstration of the feasibility of CO2-storage. When the first 'Kok-government' (the so-called 'Purple Cabinet') came into being, attention shifted to studies on CO2-storage; the central question being whether there would be sufficient potential capacity if the necessity to store CO2 would ever occur. Within this framework Novem was authorized by the Ministry of Economic Affairs to carry out an investigation program on possibilities of CO2-storage. The present publication deals with the results of these studies. The main subject of investigation were: Storage in underground formations (depleted gas fields and aquifers) and the conditions under which this is feasible; Possibilities for enhanced gas recovery by carbon dioxide injection and its

  20. Calculation of axial hydrogen redistribution on the spent fuels during interim dry storage

    International Nuclear Information System (INIS)

    Sasahara, Akihiro; Matsumura, Tetsuo

    2006-01-01

    One of the phenomena that will affect fuel integrity during a spent fuel dry storage is a hydrogen axial migration in cladding. If there is a hydrogen pickup in cladding in reactor operation, hydrogen will move from hotter to colder cladding region in the axial direction under fuel temperature gradient during dry storage. Then hydrogen beyond solubility limit in colder region will be precipitated as hydride, and consequently hydride embrittlement may take place in the cladding. In this study, hydrogen redistribution experiments were carried out to obtain the data related to hydrogen axial migration by using actually twenty years dry (air) stored spent PWR-UO 2 fuel rods of which burn-ups were 31 and 58 MWd/kg HM. From the hydrogen redistribution experiments, the heat of transport of hydrogen of zircaloy-4 cladding from twenty years dry stored spent PWR-UO 2 fuel rods were from 10.1 to 18.6 kcal/mol and they were significantly larger than that of unirradiated zircaloy-4 cladding. This means that hydrogen in irradiated cladding can move easier than that in unirradiated cladding. In the hydrogen redistribution experiments, hydrogen diffusion coefficients and solubility limit were also obtained. There are few differences in the diffusion coefficients and solubility limits between the irradiated cladding and unirradiated cladding. The hydrogen redistribution in the cladding after dry storage for forty years was evaluated by one-dimensional diffusion calculation using the measured values. The maximum values as the heat of transports, diffusion coefficients and solubility limits of the irradiated cladding and various spent fuel temperature profiles reported were used in the calculation. The axial hydrogen migration was not significant after dry storage for forty years in helium atmosphere and the maximum values as the heat of transports, diffusion coefficients and solubility limits of the unirradiated cladding gave conservative evaluation for hydrogen redistribution

  1. Yield and acidity indices of sunflower and soybean oils in function of grain drying and storage

    Directory of Open Access Journals (Sweden)

    Paulo Carteri Coradi

    2017-04-01

    Full Text Available The aim of this study was to identify the best conditions for drying and storing soybeans and sunflower grains to maintain their quality. In the first experiment, the soybeans were found to have initial moisture contents of 25 and 19% (w.b. at different drying air temperatures (75, 90, 105, and 120°C. In the second step, the soybeans were evaluated after they were stored in paper bags and plastic polyethylene at temperatures of 3, 10 and 23°C for six months. In the third experiment, sunflower grains were tested after exposure to drying air temperatures of 45, 55, 65, and 75°C, and under storage conditions of 25°C and 50%, 20°C and 60%, 30°C and 40% RH over six months in paper bags and raffia. Drying the sunflower seeds at 45°C and storing them at 30°C and 40% RH led to higher oil yields and lower acid numbers. The oil that was extracted from the acid number was higher for soybean grains that were dried down from initial concentrations of 25% water at a drying air temperature of 120°C. The air temperature in storage at 3°C favored for yield and reduction of the soybean oil acidity.

  2. Numerical modeling of the viscoplastic damage behaviour of rocks and application to underground storage facilities

    International Nuclear Information System (INIS)

    Hajdu, A.

    2003-12-01

    The long-term behavior of large, underground works of a civil engineering nature carried out in a rock mass is currently the subject of numerous studies. The object is to attain a better understanding of complex phenomena, such as the convergence of excavated cavities or the outbreak and development of damaged zones in the rock mass neighboring the works, in order to foresee them. This Ph.D. thesis is devoted to the analysis of viscoplastic strain in rocks and to the degradation of their mechanical properties with time, often referred to as deferred damage. A bibliographical record presents the current depth of understanding as regards underlying microstructural phenomena and summarizes the main theories upon which the modeling of these phenomena at the macroscopic scale is based. The formulations enabling a coupling between the viscous effects and the deferred damage are revisited and discussed in detail. One phenomenological model in particular, Lemaitre's viscoplastic constitutive damage law is retained for the numerical modeling. The calculations were performed with the help of a finite element code (CAST3M). Designs of nuclear waste disposal structures at great depth make up the subject of different case studies. The Lemaitre model, originally designed for metallic materials, is next the subject of a theoretical development of which the aim is to better adapt it to the description of the long-term mechanical behavior of rocks. The modifications focus on several points; notably that the hypotheses of anelastic strain at constant volume and of isotropy of damage are rejected. The main characteristics of time-dependent strain in rocks; in particular the phenomena of viscoplastic dilation and contraction as well as the anisotropy induced by damage to the rock matrix are reproduced by the proposed model. A parametric study is then undertaken, using the experimental results obtained on different types of rock, in order to demonstrate the model's capabilities

  3. Spent nuclear fuel integrity during dry storage - performance tests and demonstrations

    International Nuclear Information System (INIS)

    McKinnon, M.A.; Doherty, A.L.

    1997-06-01

    This report summarizes the results of fuel integrity surveillance determined from gas sampling during and after performance tests and demonstrations conducted from 1983 through 1996 by or in cooperation with the US DOE Office of Commercial Radioactive Waste Management (OCRWM). The cask performance tests were conducted at Idaho National Engineering Laboratory (INEL) between 1984 and 1991 and included visual observation and ultrasonic examination of the condition of the cladding, fuel rods, and fuel assembly hardware before dry storage and consolidation of fuel, and a qualitative determination of the effects of dry storage and fuel consolidation on fission gas release from the spent fuel rods. The performance tests consisted of 6 to 14 runs involving one or two loading, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. The nitrogen and helium backfills were sampled and analyzed to detect leaking spent fuel rods. At the end of each performance test, periodic gas sampling was conducted on each cask. A spent fuel behavior project (i.e., enhanced surveillance, monitoring, and gas sampling activities) was initiated by DOE in 1994 for intact fuel in a CASTOR V/21 cask and for consolidated fuel in a VSC-17 cask. The results of the gas sampling activities are included in this report. Information on spent fuel integrity is of interest in evaluating the impact of long-term dry storage on the behavior of spent fuel rods. Spent fuel used during cask performance tests at INEL offers significant opportunities for confirmation of the benign nature of long-term dry storage. Supporting cask demonstration included licensing and operation of an independent spent fuel storage installation (ISFSI) at the Virginia Power (VP) Surry reactor site. A CASTOR V/21, an MC-10, and a Nuclear Assurance NAC-I28 have been loaded and placed at the VP ISFSI as part of the demonstration program. 13 refs., 14 figs., 9 tabs

  4. Lipid oxidative changes in traditional dry fermented sausage Petrovská klobása during storage

    OpenAIRE

    Šojić, Branislav V.; Petrović, Ljiljana S.; Mandić, Anamarija I.; Sedej, Ivana J.; Džinić, Natalija R.; Tomović, Vladimir M.; Jokanović, Marija R.; Tasić, Tatjana A.; Škaljac, Snežana B.; Ikonić, Predrag M.

    2014-01-01

    The influence of drying and ripeninig conditions (traditional and industrial) in the production of dry fermented sausage Petrovská klobása, on fatty-acid composition and oxidative changes in lipids, during 7 months of storage, was investigated. During the storage period, the sum of unsaturated fatty acids and the content of free fatty acids were significantly higher (p

  5. Coal reserves and resources as well as potentials for underground coal gasification in connection with carbon capture and storage (CCS)

    Science.gov (United States)

    Ilse, Jürgen

    2010-05-01

    . However, these otherwise unprofitable coal deposits can be mined economically by means of underground coal gasification, during which coal is converted into a gaseous product in the deposit. The synthesis gas can be used for electricity generation, as chemical base material or for the production of petrol. This increases the usability of coal resources tremendously. At present the CCS technologies (carbon capture and storage) are a much discussed alternative to other CO2 abatement techniques like efficiency impovements. The capture and subsequent storage of CO2 in the deposits created by the actual underground gasification process seem to be technically feasible.

  6. The legal ensurance of underground ultimate storage of radioactive wastes without risk

    International Nuclear Information System (INIS)

    Prasse, R.

    1974-01-01

    1. The legal position towards the property owner: a) with a view to the freedom of property claim, b) in the light of the influence of the property owner. 2. The legal position towards the neighbouring property owners: a) resistance rights of the body corporate responsible for the ultimate storage, b) resistance rights of the neighbouring property owner. 3. The legal position towards those authorized to mine: a) mining free minerals, b) mining minerals reserved for the state. 4. The legal position towards prospectors. (orig./HP) [de

  7. Underground gas storage Uelsen: Findings from planning, building and commissioning. Part 1: Deposit; Untertagegasspeicher Uelsen: Erkenntnisse aus Planung, Bau und Inbetriebnahme. Teil 1: Lagerstaette

    Energy Technology Data Exchange (ETDEWEB)

    Wallbrecht, J.; Beckmann, H.; Reiser, H.; Wilhelm, R. [BEB Erdgas und Erdoel GmbH, Hannover (Germany)

    1998-12-31

    The underground gas storage at Uelsen which was built as a H-gas storage in a former variegated sandstone gasfield in Western Lower Saxony close to the town of Nordhorn has added to the gas supply system of the BEB Erdgas and Erdoel GmbH. The underground storage is connected to the Bunde-Rheine transport pipeline BEB-grid gas system by a 27 km pipeline and is a consequent expansion of BEB`s underground storage/transport system. Planning, building and commissioning were handled by BEB. Findings to date are described. [Deutsch] Der Untertagegasspeicher (UGS) Uelsen, der in einem ehemaligen Buntsandstein Gasfeld im westlichen Niedersachsen in der Naehe der Stadt Nordhorn als H-Gasspeicher eingerichtet wurde, hat die BEB Erdgas und Erdoel GmbH eine weitere Staerkung ihres Gasversorgungssystems erreicht. Der UGS Uelsen ist ueber eine 27 km lange Anbindungsleitung mit der zum BEB - Ferngasleitungssystems gehoerenden Bunde-Rheine Transportleitung verbunden und stellt eine konsequente Erweiterung des BEB Untertagegasspeicher-/Transportsystems dar. Planung, Bau und Inbetriebnahme erfolgten durch BEB im Rahmen einer integrierten bereichsuebergreifenden Projektbearbeitung. Die hierbei gewonnenen Erkenntnisse werden im Folgenden fuer den Untertagebereich dargestellt. (orig.)

  8. Study on underground gas storage in Europe and Central Asia; Etude sur le stockage souterrain du gaz en Europe et en Asie Centrale

    Energy Technology Data Exchange (ETDEWEB)

    Sedlacek, R. [NlfB, Germany (Germany); Rott, W. [Wintershall AG, Celle (Germany); Rokosz, W. [POGC, Poland (PL)] (and others)

    2000-07-01

    The Working Party on Gas of the United Nations Economic Commission for Europe (UN/ECE), at its sixth session in 1996, decided to undertake a study on 'Underground gas storage in Europe and Central Asia'. The study was launched by the Working Party on Gas in the recognition of the role of underground gas storage (UGS) in the creation of unified European gas market, its liberalization, security of gas supply and cooperation among gas enterprises. The data analysed by the study was collected through the comprehensive questionnaire, circulated among gas companies/organizations of the ECE member-countries. To carry out the study, a special Ad Hoc Group of Experts, representing leading gas companies of the region, was set up. The study deals with a wide range of issues related to the underground storage of gas, such as current status of UGS in Europe and Central Asia, new and emerging technologies, new and existing UGS projects, regulatory framework, cost of storage in USA and in Europe, future gas markets development. An attempt was also made to identify the UGS facilities that play (and could provide in the future) the international contract border services. (authors)

  9. Soil water storage, rainfall and runoff relationships in a tropical dry forest catchment

    Science.gov (United States)

    Farrick, Kegan K.; Branfireun, Brian A.

    2014-12-01

    In forested catchments, the exceedance of rainfall and antecedent water storage thresholds is often required for runoff generation, yet to our knowledge these threshold relationships remain undescribed in tropical dry forest catchments. We, therefore, identified the controls of streamflow activation and the timing and magnitude of runoff in a tropical dry forest catchment near the Pacific coast of central Mexico. During a 52 day transition phase from the dry to wet season, soil water movement was dominated by vertical flow which continued until a threshold soil moisture content of 26% was reached at 100 cm below the surface. This satisfied a 162 mm storage deficit and activated streamflow, likely through lateral subsurface flow pathways. High antecedent soil water conditions were maintained during the wet phase but had a weak influence on stormflow. We identified a threshold value of 289 mm of summed rainfall and antecedent soil water needed to generate >4 mm of stormflow per event. Above this threshold, stormflow response and magnitude was almost entirely governed by rainfall event characteristics and not antecedent soil moisture conditions. Our results show that over the course of the wet season in tropical dry forests the dominant controls on runoff generation changed from antecedent soil water and storage to the depth of rainfall.

  10. Validation concerns for dry storage of foreign research reactor spent nuclear fuel

    International Nuclear Information System (INIS)

    Trumble, E.F.

    1994-01-01

    Recent decisions by the Department of Energy have accelerated the need for storage options to support the return of foreign research reactor (FRR) fuel to the United States. Many of these returns consist of fuel types which contain highly enriched uranium and are aluminum clad. These attributes present many challenges not experienced in the fuel storage designs for commercial nuclear fuels where the fuels have lower enrichment and the cladding is more robust. Historically, returned FRR fuel has been stored for short periods in basins where it is cooled and then sent to be reprocessed. However, a severe lack of basin space and questionable availability of reprocessing facilities necessitates the development of other proposals. One proposed option is to store the FRR fuel in a dry state, thus reducing the corrosion problems associated with aluminum cladding. A drawback to this type of storage, however, is the lack of experimental data for this type of fuel under dry storage conditions. This lack of data has led to recent discussions over the accuracy of some of the current multigroup cross section libraries when applied to dry, fast systems of uranium and aluminum. This concern is evaluated for the specific case of Material Test Reactor (MTR) fuel (MTR is >60% of FRR fuel), a review of applicable experiments is presented and a new experiment is proposed

  11. High burnup fuel onset conditions in dry storage. Prediction of EOL rod internal pressure

    Energy Technology Data Exchange (ETDEWEB)

    Feria, F.; Herranz, L.E.

    2015-07-01

    During dry storage, cladding resistance to failure can be affected by several degrading mechanisms like creep or hydrides radial reorientation. The driving force of these effects is the stress at which the cladding is submitted. The maximum stress in the cladding is determined by the end-of-reactor-life (EOL) rod internal pressure, PEOL, at the maximum temperature attained during dry storage. Thus, PEOL sets the initial conditions of storage for potential time-dependent changes in the cladding. Based on FRAPCON-3.5 calculations, the aim of this work is to analyse the PEOL of a PWR fuel rod irradiated to burnups greater than 60 GWd/tU, where limited information is available. In order to be conservative, demanding irradiation histories have been used with a peak linear power of 44 kW/m. FRAPCON-3.5 results show an increasing exponential trend of PEOL with burnup, from which a simple correlation has been derived. The comparison with experimental data found in the literature confirms the enveloping nature of the predicted curve. Based on that, a conservative prediction of cladding stress in dry storage has been obtained. The comparison with a critical stress threshold related to hydrides embrittlement seems to point out that this issue should not be a concern at burnups below 65 GWd/tU. (Author)

  12. PBMR spent fuel bulk dry storage heat removal - HTR2008-58170

    International Nuclear Information System (INIS)

    De Wet, G. J.; Dent, C.

    2008-01-01

    A low decay heat (implying Spent Fuel (SF) pebbles older than 8-9 years) bulk dry storage section is proposed to supplement a 12-tank wet storage section. Decay heat removal by passive means must be guaranteed, taking into account the fact that dry storage vessels are under ground and inside the building footprint. Cooling takes place when ambient air (drawn downwards from ground level) passes on the outside of the 6 tanks' vessel containment (and gamma shielding), which is in a separate room inside the building, but outside PBMR building confinement and open to atmosphere. Access for loading/unloading of SF pebbles is only from the top of a tank, which is inside PBMR building confinement. No radioactive substances can therefore leak into atmosphere, as vessel design will take into account corrosion allowance. In this paper, it is shown (using CFD (Computational Fluid Dynamics) modelling and analytical analyses) that natural convection and draught induced flow combine to remove decay heat in a self-sustaining process. Decay heat is the energy source, which powers the draught inducing capability of the dry storage modular cell system: the more decay heat, the bigger the drive to expel heated air through a higher outlet and entrain cool ambient air from ground level to the bottom of the modular cell. (authors)

  13. A technique for the geometric modeling of underground surfaces: Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    Williams, R.L.

    1988-03-01

    There is a need within the Nevada Nuclear Waste Storage Investigation (NNWSI) project to develop three-dimensional surface definitions for the subterranean stratigraphies at Yucca Mountain, Nevada. The nature of the data samples available to the project require an interpolation technique that can perform well with sparse and irregularly spaced data. Following an evaluation of the relevant existing methods, a new technique, Multi-Kernel Modulation (MKM), is presented. MKM interpolates sparse and irregularly spaced data by modulating a polynomial trend surface with a linear summation of regular surfaces (kernels). A perspective discussion of MKM, Kriging, and Multiquadric Analysis reveals that MKM has the advantage of simplicity and efficiency when used with sparse samples. An example of the use of MKM to model a complex topography is presented. 24 refs., 6 figs., 2 tabs

  14. Project on effects of gas in underground storage facilities for radioactive waste (Pegasus project)

    International Nuclear Information System (INIS)

    Haijtink, B.; McMenamin, T.

    1993-01-01

    Whereas the subject of gas generation and gas release from radioactive waste repositories has gained in interest on the international scene, the Commission of the European Communities has increased its research efforts on this issue. In particular, in the fourth five-year R and D programme on management and storage of radioactive waste (1990-94), a framework has been set up in which research efforts on the subject of gas generation and migration, supported by the CEC, are brought together and coordinated. In this project, called Pegasus, about 20 organizations and research institutes are involved. The project covers theoretical and experimental studies of the processes of gas formation and possible gas release from the different waste types, LLW, ILW and HLW, under typical repository conditions in suitable geological formations such as clay, salt and granite. In this report the present status of the various research activities are described and 13 papers have been selected

  15. From clay bricks to deep underground storage; vom lehmziegel bis zum tiefenlager -- anwendung von ton

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-05-15

    This booklet issued by the Swiss National Cooperative for the Disposal of Radioactive Waste NAGRA takes a look at the use of clay strata for the storage of radioactive wastes in deep-lying repositories. First of all, a geological foray is made concerning the history of the use of clay and its multifarious uses. The characteristics of clay and its composition are examined and its formation in the geological past is explained. In particular Opalinus clay is looked at and the structures to be found are discussed. The clay's various properties and industrial uses are examined and its sealing properties are examined. Also, Bentonite clay is mentioned and work done by Nagra and co-researchers is noted.

  16. Cell growth and resistance of Lactococcus lactis subsp. lactis TOMSC161 following freezing, drying and freeze-dried storage are differentially affected by fermentation conditions.

    Science.gov (United States)

    Velly, H; Fonseca, F; Passot, S; Delacroix-Buchet, A; Bouix, M

    2014-09-01

    To investigate the effects of fermentation parameters on the cell growth and on the resistance to each step of the freeze-drying process of Lactococcus lactis subsp. lactis TOMSC161, a natural cheese isolate, using a response surface methodology. Cells were cultivated at different temperatures (22, 30 and 38°C) and pH (5·6, 6·2 and 6·8) and were harvested at different growth phases (0, 3 and 6 h of stationary phase). Cultivability and acidification activity losses of Lc. lactis were quantified after freezing, drying, 1 and 3 months of storage at 4 and 25°C. Lactococcus lactis was not damaged by freezing but was sensitive to drying and to ambient temperature storage. Moreover, the fermentation temperature and the harvesting time influenced the drying resistance of Lc. lactis. Lactococcus lactis cells grown in a whey-based medium at 32°C, pH 6·2 and harvested at late stationary phase exhibited both an optimal growth and the highest resistance to freeze-drying and storage. A better insight on the individual and interaction effects of fermentation parameters made it possible the freeze-drying and storage preservation of a sensitive strain of technological interest. Evidence on the particularly damaging effect of the drying step and the high-temperature storage is presented. © 2014 The Society for Applied Microbiology.

  17. Comparative studies on storage and drying of chips and chunks in Norway

    Energy Technology Data Exchange (ETDEWEB)

    Gjoelsjoe, S. (Norwegian Forest Research Inst. (Norway))

    1988-11-01

    Knowledge of sporulation and alteration in moisture content and dry-matter content is essential when trying to determine optimal conditions for storage of wood fuel. The object of this experiment has been to study the progression of these variables in wood fuel of varying sizes. The material used was debranched stemwood of birch. The wood was comminuted up and stored in three different sizes. The sizes were chips (length approx. 3 cm), chunkwood (approx. 8 cm) and firewood (approx. 15 cm). The fuelwood was stored in bines of 10 m{sup 3} with netting floor and netting walls. Six of the bins were covered, the remaining six were without cover. The highest temperature increase was found in chips, particularly during the first stages of storage when temperature reached approximately 30 C. The other fuel sizes had temperature close to ambient temperature. At the start of the test, moisture content was approximately 40 %. By the end of the test the moisture content was below 20% for firewood and chunkwood under cover. The moisture was measured 50 cm from the top and 50 cm from the sidewall of the bin. Whilst chips without cover had a moisture content of more than 60%. Storage under cover resulted in a higher reduction of moisture content than storage without cover. The smaller sizes exhibited the greatest difference in moisture content. The highest dry-matter loss during the storage time was found in chips stored under cover, approximately 1.2% per month. Dry-matter loss was lowest in firewood stored under cover 0.07% per month. Dry-matter loss decreased with increasing size. Spores and dust particles had the highest concentrations in chips and lowest in firewood. (12 refs., 10 figs., 8 tabs.) (au).

  18. Modeling of coupled thermodynamic and geomechanical performance of underground compressed air energy storage in lined rock caverns

    Energy Technology Data Exchange (ETDEWEB)

    Rutqvist, Jonny; Kim, Hyung-Mok; Ryu, Dong-Woo; Synn, Joong-Ho; Song, Won-Kyong

    2012-06-01

    We applied coupled nonisothermal, multiphase fluid flow and geomechanical numerical modeling to study the coupled thermodynamic and geomechanical performance of underground compressed air energy storage (CAES) in concrete-lined rock caverns. The paper focuses on CAES in lined caverns at relatively shallow depth (e.g., 100 m depth) in which a typical CAES operational pressure of 5 to 8 MPa is significantly higher than both ambient fluid pressure and in situ stress. We simulated a storage operation that included cyclic compression and decompression of air in the cavern, and investigated how pressure, temperature and stress evolve over several months of operation. We analyzed two different lining options, both with a 50 cm thick low permeability concrete lining, but in one case with an internal synthetic seal such as steel or rubber. For our simulated CAES system, the thermodynamic analysis showed that 96.7% of the energy injected during compression could be recovered during subsequent decompression, while 3.3% of the energy was lost by heat conduction to the surrounding media. Our geomechanical analysis showed that tensile effective stresses as high as 8 MPa could develop in the lining as a result of the air pressure exerted on the inner surface of the lining, whereas thermal stresses were relatively smaller and compressive. With the option of an internal synthetic seal, the maximum effective tensile stress was reduced from 8 to 5 MPa, but was still in substantial tension. We performed one simulation in which the tensile tangential stresses resulted in radial cracks and air leakage though the lining. This air leakage, however, was minor (about 0.16% of the air mass loss from one daily compression) in terms of CAES operational efficiency, and did not significantly impact the overall energy balance of the system. However, despite being minor in terms of energy balance, the air leakage resulted in a distinct pressure increase in the surrounding rock that could be

  19. South Tank Farm underground storage tank inspection using the topographical mapping system for radiological and hazardous environments

    International Nuclear Information System (INIS)

    Armstrong, G.A.; Burks, B.L.; Hoesen, S.D. van

    1997-07-01

    During the winter of 1997 the Topographical Mapping System (TMS) for hazardous and radiological environments and the Interactive Computer-Enhanced Remote-Viewing System (ICERVS) were used to perform wall inspections on underground storage tanks (USTs) W5 and W6 of the South Tank Farm (STF) at Oak Ridge National Laboratory (ORNL). The TMS was designed for deployment in the USTs at the Hanford Site. Because of its modular design, the TMS was also deployable in the USTs at ORNL. The USTs at ORNL were built in the 1940s and have been used to store radioactive waste during the past 50 years. The tanks are constructed with an inner layer of Gunite trademark that has been spalling, leaving sections of the inner wall exposed. Attempts to quantify the depths of the spalling with video inspection have proven unsuccessful. The TMS surface-mapping campaign in the STF was initiated to determine the depths of cracks, crevices, and/or holes in the tank walls and to identify possible structural instabilities in the tanks. The development of the TMS and the ICERVS was initiated by DOE for the purpose of characterization and remediation of USTs at DOE sites across the country. DOE required a three-dimensional, topographical mapping system suitable for use in hazardous and radiological environments. The intended application is mapping the interiors of USTs as part of DOE's waste characterization and remediation efforts, to obtain both baseline data on the content of the storage tank interiors and changes in the tank contents and levels brought about by waste remediation steps. Initially targeted for deployment at the Hanford Site, the TMS has been designed to be a self-contained, compact, and reconfigurable system that is capable of providing rapid variable-resolution mapping information in poorly characterized workspaces with a minimum of operator intervention

  20. Economic competitiveness of underground coal gasification combined with carbon capture and storage in the Bulgarian energy network

    Energy Technology Data Exchange (ETDEWEB)

    Nakaten, Natalie Christine

    2014-11-15

    Underground coal gasification (UCG) allows for exploitation of deep-seated coal seams not economically exploitable by conventional coal mining. Aim of the present study is to examine UCG economics based on coal conversion into a synthesis gas to fuel a combined cycle gas turbine power plant (CCGT) with CO2 capture and storage (CCS). Thereto, a techno-economic model is developed for UCG-CCGT-CCS costs of electricity (COE) determination which, considering sitespecific data of a selected target area in Bulgaria, sum up to 72 Euro/MWh in total. To quantify the impact of model constraints on COE, sensitivity analyses are undertaken revealing that varying geological model constraints impact COE with 0.4% to 4%, chemical with 13%, technical with 8% to 17% and market-dependent with 2% to 25%. Besides site-specific boundary conditions, UCG-CCGT-CCS economics depend on resources availability and infrastructural characteristics of the overall energy system. Assessing a model based implementation of UCG-CCGT-CCS and CCS power plants into the Bulgarian energy network revealed that both technologies provide essential and economically competitive options to achieve the EU environmental targets and a complete substitution of gas imports by UCG synthesis gas production.

  1. Initial laboratory studies into the chemical and radiological aging of organic materials in underground storage tanks at the Hanford Complex

    International Nuclear Information System (INIS)

    Samuels, W.D.; Camaioni, D.M.; Babad, H.

    1994-01-01

    The underground storage tanks at the Hanford Complex contain wastes generated over many years from plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct bearing on several specific safety issues, including potential energy releases from these tanks. The major portion of organic materials that have been added to the tanks consists of tributyl phosphate, dibutyl phosphate, butyl alcohol, hexone (methyl isobutyl ketone), normal paraffin hydrocarbons (NPH), ethylenediaminetetraacetic acid (EDTA), hydroxyethylethylenediaminetriadetic acid (HEDTA), other complexants, and lesser quantities of ion exchange polymers and minor organic compounds. A study of how thermal and radiological processes that may have changed the composition of organic tanks constituents has been initiated after a review of the open literature revealed little information was available about the rates and products of these processes under basic pH conditions. This paper will detail the initial findings as they relate to gas generation, e.g. H 2 , CO, NH 3 , CH 4 , and to changes in the composition of the organic and inorganic components brought about by ''Aging'' processes

  2. Assessment of ground-water contamination from a leaking underground storage tank at a defense supply center near Richmond, Virginia

    International Nuclear Information System (INIS)

    Powell, J.D.; Wright, W.G.

    1990-01-01

    During 1988-89, 24 wells were installed in the vicinity of the post-exchange gasoline station on the Defense General Supply Center, near Richmond, Virginia, to collect and analyze groundwater samples for the presence of gasoline contamination from a leaking underground storage tank. Concentrations of total petroleum hydrocarbons and benzene were as high as 8.2 mg/L and 9,000 microg/L, respectively, in water from wells in the immediate vicinity of the former leaking tank, and benzene concentrations were as high as 2,300 microg/L in a well 600 ft down gradient from the gasoline station. Groundwater flow rate are estimated to be about 60 to 80 ft/yr; on the basis of these flow rates, the contaminants may have been introduced into the groundwater as long as 7-10 yrs ago. Groundwater might infiltrate a subsurface storm sewer, where the sewer is below the water table, and discharge into a nearby stream. Preliminary risk assessment for the site identified no potential human receptors to the groundwater contamination because there were no groundwater users identified in the area. Remediation might be appropriate if exposure of future potential users is concern. Alternatives discussed for remediation of groundwater contamination in the upper aquifer at the PX Service Station include no-action, soil vapor extraction, and groundwater pumping and treatment alternatives

  3. Economic competitiveness of underground coal gasification combined with carbon capture and storage in the Bulgarian energy network

    International Nuclear Information System (INIS)

    Nakaten, Natalie Christine

    2014-01-01

    Underground coal gasification (UCG) allows for exploitation of deep-seated coal seams not economically exploitable by conventional coal mining. Aim of the present study is to examine UCG economics based on coal conversion into a synthesis gas to fuel a combined cycle gas turbine power plant (CCGT) with CO2 capture and storage (CCS). Thereto, a techno-economic model is developed for UCG-CCGT-CCS costs of electricity (COE) determination which, considering sitespecific data of a selected target area in Bulgaria, sum up to 72 Euro/MWh in total. To quantify the impact of model constraints on COE, sensitivity analyses are undertaken revealing that varying geological model constraints impact COE with 0.4% to 4%, chemical with 13%, technical with 8% to 17% and market-dependent with 2% to 25%. Besides site-specific boundary conditions, UCG-CCGT-CCS economics depend on resources availability and infrastructural characteristics of the overall energy system. Assessing a model based implementation of UCG-CCGT-CCS and CCS power plants into the Bulgarian energy network revealed that both technologies provide essential and economically competitive options to achieve the EU environmental targets and a complete substitution of gas imports by UCG synthesis gas production.

  4. Dry Matter Losses and Greenhouse Gas Emissions From Outside Storage of Short Rotation Coppice Willow Chip.

    Science.gov (United States)

    Whittaker, Carly; Yates, Nicola E; Powers, Stephen J; Misselbrook, Tom; Shield, Ian

    This study examined the dry matter losses and the greenhouse gas (GHG) concentrations within two short rotation coppice (SRC) willow wood chip storage heaps. One heap was built on a grassland area (East Midlands) and the other (Rothamsted) on a concrete hard standing. A series of 1- and 3-m probes were embedded in the heaps in order to retrieve gas samples for analysis, and pre-weighed net bags were positioned in the core of the heap to detect dry matter losses. The bagged samples showed dry matter losses of 18 and 19 % in the East Midlands and Rothamsted heaps after 210 and 97 days storage, respectively. The Rothamsted heap showed a whole-heap dry matter loss of 21 %. During this time, the wood chips dried from 54 to 39 % moisture content in the East Midlands heap and 50 to 43 % at Rothamsted. The results from analysing the whole Rothamsted heap indicated an overall loss of 1.5 GJ per tonne stored, although measurements from bagged samples in the core suggested that the chips dried sufficiently to have a minimal energy loss from storage. The process of mixing the heap, however, led to incorporation of wet outer layers and hence the average moisture content was higher in an average sample of chip. After establishment of the heaps, the temperature rose rapidly and this correlated with a peak in carbon dioxide (CO 2 ) concentration within the heap. A peak in methane (CH 4 ) concentration was also detected in both heaps, though more noticeably in the East Midlands heap after around 55 days. In both instances, the peak CH 4 concentration occurred as CO 2 concentrations dropped, suggesting that after an active period of aerobic decomposition in the first 2 months of storage, the conditions in the heap became anaerobic. The results from this study suggest that outside wood chip storage is not an efficient method of storing biomass, though this may be location-specific as there are some studies showing lower dry matter losses. It is necessary to explore other

  5. The maximum allowable temperature of zircaloy-2 fuel cladding under dry storage conditions

    International Nuclear Information System (INIS)

    Mayuzumi, M.; Yoshiki, S.; Yasuda, T.; Nakatsuka, M.

    1990-09-01

    Japan plans to reprocess and reutilise the spent nuclear fuel from nuclear power generation. However, the temporary storage of spent fuel is assuming increasing importance as a means of ensuring flexibility in the nuclear fuel cycle. Our investigations of various methods of storage have shown that casks are the most suitable means of storing small quantities of spent fuel of around 500 t, and research and development are in progress to establish dry storage technology for such casks. The soundness of fuel cladding is being investigated. The most important factor in evaluating soundness in storage under inert gas as currently envisaged is creep deformation and rupture, and a number of investigations have been made of the creep behaviour of cladding. The present study was conducted on the basis of existing in-house results in collaboration with Nippon Kakunenryo Kaihatsu KK (Nippon Nuclear Fuel Department Co.), which has hot lab facilities. Tests were run on the creep deformation behaviour of irradiated cladding, and the maximum allowable temperature during dry storage was investigated. (author)

  6. Final Technical Report: Imaging a Dry Storage Cask with Cosmic Ray Muons

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Haori; Hayward, Jason; Can, Liao; Liu, Zhengzhi

    2018-03-31

    The goal of this project is to build a scaled prototype system for monitoring used nuclear fuel (UNF) dry storage casks (DSCs) through cosmic ray muon imaging. Such a system will have the capability of verifying the content inside a DSC without opening it. Because of the growth of the nuclear power industry in the U.S. and the policy decision to ban reprocessing of commercial UNF, the used fuel inventory at commercial reactor sites has been increasing. Currently, UNF needs to be moved to independent spent fuel storage installations (ISFSIs), as its inventory approaches the limit on capacity of on-site wet storage. Thereafter, the fuel will be placed in shipping containers to be transferred to a final disposal site. The ISFSIs were initially licensed as temporary facilities for ~20-yr periods. Given the cancellation of the Yucca mountain project and no clear path forward, extended dry-cask storage (~100 yr.) at ISFSIs is very likely. From the point of view of nuclear material protection, accountability and control technologies (MPACT) campaign, it is important to ensure that special nuclear material (SNM) in UNF is not stolen or diverted from civilian facilities for other use during the extended storage.

  7. Cytogenetic effects of electron-beam radiation on dry seed storage

    International Nuclear Information System (INIS)

    Baojiang, G.; Qishen, P.; Kohlman, A.

    1989-01-01

    Dry seeds of Viciafaba were exposed to 5 MeV electron beam (10–30 Krad) and stored afterwards during 20,40 and 60 days- Induction of chromosomal aberrations in root-tip cells of irradiated seeds has been found dose-dependent. The frequency of chromosomal aberrations (particularly, the bridges and the rings) and the frequency of micronucleated cells is proportional to the length of storage time, but is not significantly influenced by low temperatures (0–6°C) during storage. (author)

  8. Retention of short chain fatty acids under drying and storage conditions

    Directory of Open Access Journals (Sweden)

    Alexandre Santos Souza

    2011-09-01

    Full Text Available Cheese whey permeate was used as a substrate for the fermentation of Propionibacterium freudenreichi PS1 for the production of short chain fatty acids, components of the bio-aroma of Swiss cheese. The liquid bio-aroma was encapsulated by spray drying under different conditions of air inlet temperature and feed rate. A study was carried out on the stability of the bio-aroma during storage in laminated packages at 30 °C for 96 days using the product showing the greatest retention of acetic and propionic acids. The results showed that the best drying conditions were an air entrance temperature of 180 °C and a feed rate of 24 g/min resulting in particles with a smooth surface and few invaginations and micro-fissures. However, 72% of the acetic acid and 80% of the propionic acid were lost during storage showing that the wall material used was inadequate to guarantee product stability.

  9. Survival of spray-dried Lactobacillus kefir is affected by different protectants and storage conditions.

    Science.gov (United States)

    Golowczyc, Marina A; Gerez, Carla L; Silva, Joana; Abraham, Analía G; De Antoni, Graciela L; Teixeira, Paula

    2011-04-01

    Survival of two Lactobacillus kefir strains after spray drying in reconstituted skim milk with or without the addition of 12.5 g monosodium glutamate/l, 20 g sucrose/l, or 20 g fructo-oligosaccharides (FOS)/l and during subsequent storage under different conditions of temperature (20 and 30°C) and relative humidity (RH) (0, 11 and 23%) was evaluated. After being dried, L. kefir 8321 and L. kefir 8348 had a decrease in viability of 0.29 and 0.70 log cfu/ml respectively, while the addition of different protectants improved the survival of both strains significantly. During storage, bacterial survival was significantly higher under lower conditions of RH (0-11%), and monosodium glutamate and FOS proved to be the best protectants.

  10. Sustainable Irrigation Allocation Model for Dry and Wet Periods using Reservoir Storage and Inflow

    Science.gov (United States)

    Surianarayanan, S.; Suribabu, C. R.; Ramakrishnan, K.

    2017-07-01

    The dry period agriculture is inevitable both for the farmers for their earning, and for the soil for its fertility by crop-rotation. In tropical countries like INDIA, dry period agriculture becomes difficult because of less (or) no rain fall. Hence a simple water balancing model for irrigation scheduling, using the measure “Volumetric Reliability” is prepared in this paper, with the storage and inflow of a reservoir both for the dry and wet periods. The case-study is done for a reservoir in INDIA with thirty one years of hydrological data(from 1982 to 2012). The objective of this paper is to prepare a simple water balance model taking 10 days periods of demand and supply for ID crop(Irrigated Dry crop, ground nut) with usage of volumetric reliability concept for the periods of deficiency and adoption of less water requirement crops to reduce the water-stress during critical periods of crop growth, and finally arrive at a feasible allocation schedule for the success of agriculture and the yield throughout the year both for wet and dry crops with the available storage on the start of irrigation for a particular year. The reservoir is divided for storages such as full, deficient and critical storages. The starting storage for the dry period from January is used after adequate allocation for wet crops, the quantity for riparian rights and for drinking water, for the sustainability. By the water-balancing, the time-series for thirty one years, it is found that for twenty two years the demand for the ID crops is satisfied with the storage in the reservoir, and in the remaining years of deficient inflows, for three years (1986,1996,2004)the demand is managed by using the safe reliability factor for demand which can nullify the deficit in demand for the whole supply period. But it is genuine to assure that the reduction in the amount of water for each 10 days periods should not exceed the survival limit of the crop. Necessary soil-moisture must be ensured in the crop

  11. Characterizing and packaging BN-350 spent fuel for long-term dry storage

    International Nuclear Information System (INIS)

    Lambert, J. D. B.; Bolshinsky, I.; Haues, S.L.; Allen, K.J.; Howden, E.A.; Hill, R.N.; Planchon, H.P.; Staples, P.; Karaulov, V.N.; Blynskij, A.P.; Yakovlev, I.K.; Maev, V.; Dumchev, I. A.

    2000-01-01

    The Republic of Kazakhstan is being assisted by the U.S. Department of Energy in preparing spent fuel from the BN-350 fast reactor for long term dry storage. Argonne National Laboratory was assigned responsibility for the physical and nuclear characterization of the spent fuel, for the design and safety analysis of 6-pac and 4-pac canisters used to contain spent fuel assemblies for storage, and for the design, testing and installation of a closure station at the reactor in which the canisters of fuel are dried, filled with inert gas and welded shut. This paper briefly describes the specialized components and equipment used, the process followed, and experience gained in packaging the spent fuel. Olsen et al and Schaefer separately discuss overall safety and criticality considerations of the packaging process in parallel papers to this conference

  12. Cosmic ray muon computed tomography of spent nuclear fuel in dry storage casks

    Science.gov (United States)

    Poulson, D.; Durham, J. M.; Guardincerri, E.; Morris, C. L.; Bacon, J. D.; Plaud-Ramos, K.; Morley, D.; Hecht, A. A.

    2017-01-01

    Radiography with cosmic ray muon scattering has proven to be a successful method of imaging nuclear material through heavy shielding. Of particular interest is monitoring dry storage casks for diversion of plutonium contained in spent reactor fuel. Using muon tracking detectors that surround a cylindrical cask, cosmic ray muon scattering can be simultaneously measured from all azimuthal angles, giving complete tomographic coverage of the cask interior. This paper describes the first application of filtered back projection algorithms, typically used in medical imaging, to cosmic ray muon scattering imaging. The specific application to monitoring spent nuclear fuel in dry storage casks is investigated via GEANT4 simulations. With a cylindrical muon tracking detector surrounding a typical spent fuel cask, simulations indicate that missing fuel bundles can be detected with a statistical significance of ∼ 18 σ in less than two days exposure and a sensitivity at 1σ to a 5% missing portion of a fuel bundle. Potential detector technologies and geometries are discussed.

  13. An assessment of temperature history on concrete silo dry storage system for CANDU spent fuel

    International Nuclear Information System (INIS)

    Lee, Dong-Gyu; Sung, Nak-Hoon; Park, Jea-Ho; Chung, Sung-Hwan

    2016-01-01

    Highlights: • We performed thermal analysis to predict the temperature distribution in the concrete silo. • Thermal analysis of the concrete silo was based on CFD code. • Temperature distribution and history for storage period was presented. • Thermal analysis results and test results agreed well. • The correlations can predict the maximum fuel temperature over storage period. - Abstract: Concrete silo is a dry storage system for spent fuel generated from CANDU reactors. The silo is designed to remove passively the decay heat from spent fuel, as well as to secure the integrity of spent fuel during storage period. Dominant heat transfer mechanisms must be characterized and validated for the thermal analysis model of the silo, and the temperature history along storage period could be determined by using the validated thermal analysis model. Heat transfer characteristics on the interior and exterior of fuel basket in the silo were assessed to determine the temperature history of silo, which is necessary for evaluating the long-term degradation behavior of CANDU spent fuel stored in the silo. Also a methodology to evaluate the temperature history during dry storage period was proposed in this study. A CFD model of fuel basket including fuel bundles was suggested and temperature difference correlation between fuel bundles and silo’s internal member, as a function of decay heat of fuel basket considering natural convection and radiation heat transfer, was deduced. Temperature difference between silo’s internal cavity and ambient air was determined by using a concept of thermal resistance, which was validated by CFD analysis. Fuel temperature was expressed as a function of ambient temperature and decay heat of fuel basket in the correlation, and fuel temperature along storage period was determined. Therefore, it could be used to assess the degradation behavior of spent fuel by applying the degradation mechanism expressed as a function of spent fuel

  14. Select Generic Dry-Storage Pilot Plant Design for Safeguards and Security by Design (SSBD) per Used Fuel Campaign

    Energy Technology Data Exchange (ETDEWEB)

    Demuth, Scott Francis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sprinkle, James K. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-05-26

    As preparation to the year-end deliverable (Provide SSBD Best Practices for Generic Dry-Storage Pilot Scale Plant) for the Work Package (FT-15LA040501–Safeguards and Security by Design for Extended Dry Storage), the initial step was to select a generic dry-storage pilot plant design for SSBD. To be consistent with other DOE-NE Fuel Cycle Research and Development (FCR&D) activities, the Used Fuel Campaign was engaged for the selection of a design for this deliverable. For the work Package FT-15LA040501–“Safeguards and Security by Design for Extended Dry Storage”, SSBD will be initiated for the Generic Dry-Storage Pilot Scale Plant described by the layout of Reference 2. SSBD will consider aspects of the design that are impacted by domestic material control and accounting (MC&A), domestic security, and international safeguards.

  15. Conceptual design report for the ICPP spent nuclear fuel dry storage project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    The conceptual design is presented for a facility to transfer spent nuclear fuel from shipping casks to dry storage containers, and to safely store those containers at ICPP at INEL. The spent fuels to be handled at the new facility are identified and overall design and operating criteria established. Physical configuration of the facility and the systems used to handle the SNF are described. Detailed cost estimate for design and construction of the facility is presented.

  16. Design features for enhancing international safeguards of AFR dry storage for spent LWR fuel

    International Nuclear Information System (INIS)

    Roberts, F.P.; Harms, N.L.

    1985-05-01

    The Pacific Northwest Laboratory has performed a study for the Nuclear Regulatory Commission to identify and analyze design features that can facilitate the implementation of IAEA safeguards at facilities for dry storage of light water reactor spent fuels. Specific design features are identified that can enhance nuclear material flow and inventory verification. These are assessed from the viewpoint of safeguards effectiveness and possible impacts on the IAEA and the operator of the AFR facility. 11 refs., 3 figs., 2 tabs

  17. Effect of drying treatments and storage stability on quality characteristics of bael powder.

    Science.gov (United States)

    Sagar, V R; Kumar, Rajesh

    2014-09-01

    Dehydration of bael pulp in to powder form is a challenging operation, mainly due to the sticky issue of bael pulp and caking of powder during handling and storage. To overcome on this problem maltodextrin MD (drying aid) and tricalcium phosphate, TCP (anti caking agent) were added to the bael pulp at four levels along with control and dried in a mechanical drier into thin layer at 58 ± 2 °C for 12 h, to obtain a moisture content of 4-5 % in dehydrated pulp. The dehydrated bael pulp was grounded in a laboratory powder mill and sieve with 30 mesh sieve. The powder was packed in 150gauge PP, 400gauge LDPE and 200gauge HDPE pouches and was stored at low temperature (7 °C) and ambient condition (18-35 °C) up to 6 months for storage study. The powder was evaluated for its quality characteristics in respect of acidity, sugars, antioxidant, phenol, ascorbic acid, non- enzymatic browning (NEB) before packaging and during storage. The amount of MD and TCP required to reduce powder stickiness and caking were optimized on the powder properties. The amount of MD (0.25 kg per kg dry bael solids) and TCP (0.15 kg per kg dry bael solids) with the values of degree of caking (19.24 %) and stickiness point temperature (45.4 °C) were found to be optimum for reducing the powder stickiness, caking and nutritional parameters. The adsorption isotherm of bael powder was found to be type-II sigmoid and 200 g HDPE as packaging material followed by storage at low temperature were selected as best process.

  18. Possibility for dry storage of the WWR-K reactor spent fuel

    International Nuclear Information System (INIS)

    Arinkin, F.M.; Belyakova, E.A.; Gizatulin, Sh.Kh.; Khromushin, I.V.; Koltochik, S.N.; Maltseva, R.M.; Medvedeva, Z.V.; Petukhov, V.K.; Soloviev, Yu.A.; Zhotabaev, Zh.R.

    2000-01-01

    This work is devoted to development of the way for dry storage of spent fuel of the WWR-K reactor. Residual energy release in spent fuel element assembly was determined via fortune combination of calculations and experiments. The depth of fission product occurrence relative to the fuel element shroud surface was found experimentally. The time of fission product release to the fuel element shroud surface was estimated. (author)

  19. Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage

    International Nuclear Information System (INIS)

    Qu, Jianmin; Bazant, Zdenek; Jacobs, Laurence; Guimaraes, Maria

    2015-01-01

    Alkali-silica reaction (ASR) is a deleterious chemical process that may occur in cement-based materials such as mortars and concretes, where the hydroxyl ions in the highly alkaline pore solution attack the siloxane groups in the siliceous minerals in the aggregates. The reaction produces a cross-linked alkali-silica gel. The ASR gel swells in the presence of water. Expansion of the gel results in cracking when the swelling-induced stress exceeds the fracture toughness of the concrete. As the ASR continues, cracks may grow and eventually coalesce, which results in reduced service life and a decrease safety of concrete structures. Since concrete is widely used as a critical structural component in dry cask storage of used nuclear fuels, ASR damage poses a significant threat to the sustainability of long term dry cask storage systems. Therefore, techniques for effectively detecting, managing and mitigating ASR damage are needed. Currently, there are no nondestructive methods to accurately detect ASR damage in existing concrete structures. The only current way of accurately assessing ASR damage is to drill a core from an existing structure, and conduct microscopy on this drilled cylindrical core. Clearly, such a practice is not applicable to dry cask storage systems. To meet these needs, this research is aimed at developing (1) a suite of nonlinear ultrasonic quantitative nondestructive evaluation (QNDE) techniques to characterize ASR damage, and (2) a physics-based model for ASR damage evolution using the QNDE data. Outcomes of this research will provide a nondestructive diagnostic tool to evaluate the extent of the ASR damage, and a prognostic tool to estimate the future reliability and safety of the concrete structures in dry cask storage systems

  20. Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage

    Energy Technology Data Exchange (ETDEWEB)

    Qu, Jianmin [Northwestern Univ., Evanston, IL (United States); Bazant, Zdenek [Northwestern Univ., Evanston, IL (United States); Jacobs, Laurence [Georgia Inst. of Technology, Atlanta, GA (United States); Guimaraes, Maria [Electrical Power Research Institute, Palo Alto, CA (United States)

    2015-11-30

    Alkali-silica reaction (ASR) is a deleterious chemical process that may occur in cement-based materials such as mortars and concretes, where the hydroxyl ions in the highly alkaline pore solution attack the siloxane groups in the siliceous minerals in the aggregates. The reaction produces a cross-linked alkali-silica gel. The ASR gel swells in the presence of water. Expansion of the gel results in cracking when the swelling-induced stress exceeds the fracture toughness of the concrete. As the ASR continues, cracks may grow and eventually coalesce, which results in reduced service life and a decrease safety of concrete structures. Since concrete is widely used as a critical structural component in dry cask storage of used nuclear fuels, ASR damage poses a significant threat to the sustainability of long term dry cask storage systems. Therefore, techniques for effectively detecting, managing and mitigating ASR damage are needed. Currently, there are no nondestructive methods to accurately detect ASR damage in existing concrete structures. The only current way of accurately assessing ASR damage is to drill a core from an existing structure, and conduct microscopy on this drilled cylindrical core. Clearly, such a practice is not applicable to dry cask storage systems. To meet these needs, this research is aimed at developing (1) a suite of nonlinear ultrasonic quantitative nondestructive evaluation (QNDE) techniques to characterize ASR damage, and (2) a physics-based model for ASR damage evolution using the QNDE data. Outcomes of this research will provide a nondestructive diagnostic tool to evaluate the extent of the ASR damage, and a prognostic tool to estimate the future reliability and safety of the concrete structures in dry cask storage systems

  1. Application of the BEPU methodology to assess fuel performance in dry storage

    International Nuclear Information System (INIS)

    Feria, F.; Herranz, L.E.

    2017-01-01

    Highlights: • Application of the BEPU methodology to estimate the cladding stress in dry storage. • The stress predicted is notably affected by the irradiation history. • Improvements of FGR modelling would significantly enhance the stress estimates. • The prediction uncertainty should not be disregarded when assessing clad integrity. - Abstract: The stress at which fuel cladding is submitted in dry storage is the driving force of the main degrading mechanisms postulated (i.e., embrittlement due to hydrides radial reorientation and creep). Therefore, a sound assessment is mandatory to reliably predict fuel performance under the dry storage prevailing conditions. Through fuel rod thermo-mechanical codes, best estimate calculations can be conducted. Precision of predictions depends on uncertainties affecting the way of calculating the stress, so by using uncertainty analysis an upper bound of stress can be determined and compared to safety limits set. The present work shows the application of the BEPU (Best Estimate Plus Uncertainty) methodology in this field. Concretely, hydrides radial reorientation has been assessed based on stress predictions under challenging thermal conditions (400 °C) and a stress limit of 90 MPa. The computational tools used to do that are FRAPCON-3xt (best estimate) and Dakota (uncertainty analysis). The methodology has been applied to a typical PWR fuel rod highly irradiated (65 GWd/tU) at different power histories. The study performed allows concluding that both the power history and the prediction uncertainty should not be disregarded when fuel rod integrity is evaluated in dry storage. On probabilistic bases, a burnup of 60 GWd/tU is found out as an acceptable threshold even in the most challenging irradiation conditions considered.

  2. Cna 1 spent fuel element interim dry storage system thermal analysis

    International Nuclear Information System (INIS)

    Hilal, R. E; Garcia, J. C; Delmastro, D. F

    2006-01-01

    At the moment, the Atucha I Nuclear Power Plant (Cnea-I) located in the city of Lima, has enough room to store its spent fuel (Sf) in their two pools spent fuel until about 2015.In case of life extension a spend fuel element interim dry storage system is needed.Nucleolectrica Argentina S.A. (N A-S A) and the Comision Nacional de Energia Atomica (Cnea), have proposed different interim dry storage systems.These systems have to be evaluated in order to choose one of them.The present work's objective is the thermal analysis of one dry storage alternative for the Sf element of Cna 1.In this work a simple model was developed and used to perform the thermal calculations corresponding to the system proposed by Cnea.This system considers the store of sealed containers with 37 spent fuels in concrete modules.Each one of the containers is filled in the pool houses and transported to the module in a transference cask with lead walls.Fulfill the maximum cladding temperature requirement ( [es

  3. Pectin Methyl Esterase Activity Change in Intermediate Moisture Sun-Dried Figs after Storage

    Directory of Open Access Journals (Sweden)

    Dilek Demirbüker Kavak

    2015-12-01

    Full Text Available Intermediate moisture fruits can be obtained by rehydrating dried fruits. Intermediate moisture fruits are suitable for direct consumption compared to dry fruits and can be directly used in the production of various products such as bakery products, dairy products and candies. Aim of this study is to compare the pectin methyl esterase (PME activity of intermediate moisture figs which causes softening of the texture and to compare their microbial stability after 3 months storage period. For this purpose, dried figs were rehydrated in 30 and 80° C water until they reach 30% moisture content. Rehydrated samples were stored for 3 months at +4°C. Results showed that there was no statistically significant difference between the control samples and the samples rehydrated at 80°C according to the total viable counts. At the end of the storage period, results of residual PME activity in control samples was 24.1 μmol COOH min-1g-1, while it was found 17.4 μmol COOH min-1g-1 in samples rehydrated at 80°C. As a result rehydration conducted at 80°C provided 28% reduction in PME activity compared to the control samples rehydrated at 30°C, although it did not affect the microbial load significantly after storage.

  4. A Preliminary Study on Rock Bed Heat Storage from Biomass Combustion for Rice Drying

    Science.gov (United States)

    Nelwan, L. O.; Wulandani, D.; Subrata, I. D. M.

    2018-05-01

    One of the main constraints of biomass fuel utilization in a small scale rice drying system is the operating difficulties related to the adjustment of combustion/feeding rate. Use of thermal storage may reduce the problem since combustion operation can be accomplished in a much shorter time and then the use of heat can be regulated by simply adjusting the air flow. An integrated biomass furnace-rock bed thermal storage with a storage volume of 540 L was designed and tested. There were four experiments conducted in this study. Charging was performed within 1-2 hours with a combustion rate of 11.5-15.5 kg/h. In discharging process, the mixing of air passing through the rock bed and ambient air were regulated by valves. Without adjusting the valve during the discharging process, air temperature increased up to 80°C, which is not suitable for rice batch drying process. Charging with sufficiently high combustion rate (14 kg/h) within 1 hour continued by adjusting the valve during discharging process below 60°C increased the discharge-charge time ratio (DCTR) up to 5.33 at average air temperature of 49°C and ambient temperature of 33°C.The efficiency of heat discharging was ranged from 34.5 to 45.8%. From the simulation, as much as 156.8-268.8 kg of rice was able to be dried by the discharging conditions.

  5. SCALE6.1 Hybrid Shielding Methodology For The Spent Fuel Dry Storage

    International Nuclear Information System (INIS)

    Matijevic, M.; Pevec, D.; Trontl, K.

    2015-01-01

    The SCALE6.1/MAVRIC hybrid deterministic-stochastic shielding methodology was used for dose rates calculation of the generic spent fuel dry storage installation. The neutron-gamma dose rates around the cask array were calculated over a large problem domain in order to determine the boundary of the controlled area. The FW-CADIS methodology, based on the deterministic forward and adjoint solution over the phase - space, was used for optimized, global Monte Carlo results over the mesh tally. The cask inventory was modeled as homogenized material corresponding to 20 fuel assemblies from a standard mid - sized PWR reactor. The global simulation model was an array of 32 casks in 2 rows with concrete foundations and external air, which makes a large spatial domain for shielding calculations. The dose rates around the casks were determined using FW-CADIS method with weighted adjoint source and mesh tally covering a portion of spatial domain of interest. The conservatively obtained dose rates give the upper boundary, since the activation reduction of sources was not taken into account when sequential filling of the dry storage will start. The effective area of the dry storage installation can be additionally reduced with lowering concrete foundation under the ground, embankment raising, and with extra concrete walls, that would additionally lower the dominant gamma dose rates. (author).

  6. Effect of Packaging Materials on Orthosiphon Stamineus Dried-Leaf Quality During Storage

    Science.gov (United States)

    Norawanis, A. R.; Shaari, A. R.; Leng, L. Y.

    2018-03-01

    The experiment was conducted to determine the effects on the total phenolic content, antioxidant capacity, moisture content and total different color (ΔE) when the O. stamineus dried whole-leaf were packed in different packaging materials (plastic bag, paper bag and glass container) and stored under room temperature (±25 °C) and relative humidity (±65 %RH) for 8 weeks. The total phenolic compounds and antioxidant activity were measured using the Folin-Ciocalteu method and 2,2-diphenyl-1-picrylhydrazyl (DPPH) free radical scavenging activity assay respectively, and analyzed using UV/VIS Spectrophotometer. The moisture content changes were examined using a moisture analyzer and the color changes were analyzed using colorimeter. The results showed that packing O. stamineus dried whole-leaf in different packaging materials significantly affected the herbal leaves quality. After 8 weeks of storage period, the total phenolic content and antioxidant capacity exhibited the increase values during storage. Meanwhile, the moisture content of the samples decreased by storage period for the samples packed in plastic bag and glass container. The moisture content of the samples packed in the paper bag fluctuated along the 8 weeks of storage period. The total different color (ΔE) of the O. stamineus dried whole-leaf increased by storage period. The highest changes of ΔE belonged to the samples packed in the glass container, followed by paper and plastic bags. The selection of the packaging materials can be considered as an important element to control the quality of raw herbal materials for further processing and the herbal finished products.

  7. Seed storage at elevated partial pressure of oxygen, a fast method for analysing seed ageing under dry conditions

    Science.gov (United States)

    Groot, S. P. C.; Surki, A. A.; de Vos, R. C. H.; Kodde, J.

    2012-01-01

    Background and Aims Despite differences in physiology between dry and relative moist seeds, seed ageing tests most often use a temperature and seed moisture level that are higher than during dry storage used in commercial practice and gene banks. This study aimed to test whether seed ageing under dry conditions can be accelerated by storing under high-pressure oxygen. Methods Dry barley (Hordeum vulgare), cabbage (Brassica oleracea), lettuce (Lactuca sativa) and soybean (Glycine max) seeds were stored between 2 and 7 weeks in steel tanks under 18 MPa partial pressure of oxygen. Storage under high-pressure nitrogen gas or under ambient air pressure served as controls. The method was compared with storage at 45 °C after equilibration at 85 % relative humidity and long-term storage at the laboratory bench. Germination behaviour, seedling morphology and tocopherol levels were assessed. Key Results The ageing of the dry seeds was indeed accelerated by storing under high-pressure oxygen. The morphological ageing symptoms of the stored seeds resembled those observed after ageing under long-term dry storage conditions. Barley appeared more tolerant of this storage treatment compared with lettuce and soybean. Less-mature harvested cabbage seeds were more sensitive, as was the case for primed compared with non-primed lettuce seeds. Under high-pressure oxygen storage the tocopherol levels of dry seeds decreased, in a linear way with the decline in seed germination, but remained unchanged in seeds deteriorated during storage at 45 °C after equilibration at 85 % RH. Conclusions Seed storage under high-pressure oxygen offers a novel and relatively fast method to study the physiology and biochemistry of seed ageing at different seed moisture levels and temperatures, including those that are representative of the dry storage conditions as used in gene banks and commercial practice. PMID:22967856

  8. Seed storage at elevated partial pressure of oxygen, a fast method for analysing seed ageing under dry conditions.

    Science.gov (United States)

    Groot, S P C; Surki, A A; de Vos, R C H; Kodde, J

    2012-11-01

    Despite differences in physiology between dry and relative moist seeds, seed ageing tests most often use a temperature and seed moisture level that are higher than during dry storage used in commercial practice and gene banks. This study aimed to test whether seed ageing under dry conditions can be accelerated by storing under high-pressure oxygen. methods: Dry barley (Hordeum vulgare), cabbage (Brassica oleracea), lettuce (Lactuca sativa) and soybean (Glycine max) seeds were stored between 2 and 7 weeks in steel tanks under 18 MPa partial pressure of oxygen. Storage under high-pressure nitrogen gas or under ambient air pressure served as controls. The method was compared with storage at 45 °C after equilibration at 85 % relative humidity and long-term storage at the laboratory bench. Germination behaviour, seedling morphology and tocopherol levels were assessed. The ageing of the dry seeds was indeed accelerated by storing under high-pressure oxygen. The morphological ageing symptoms of the stored seeds resembled those observed after ageing under long-term dry storage conditions. Barley appeared more tolerant of this storage treatment compared with lettuce and soybean. Less-mature harvested cabbage seeds were more sensitive, as was the case for primed compared with non-primed lettuce seeds. Under high-pressure oxygen storage the tocopherol levels of dry seeds decreased, in a linear way with the decline in seed germination, but remained unchanged in seeds deteriorated during storage at 45 °C after equilibration at 85 % RH. Seed storage under high-pressure oxygen offers a novel and relatively fast method to study the physiology and biochemistry of seed ageing at different seed moisture levels and temperatures, including those that are representative of the dry storage conditions as used in gene banks and commercial practice.

  9. Dry oxidation behaviour of metallic containers during long term interim storages

    International Nuclear Information System (INIS)

    Desgranges, C.; Terlain, A.; Bertrand, N.; Gauvain, D.

    2004-01-01

    Low-alloyed steels or carbon steels are considered candidate materials for the fabrication of some nuclear waste package containers for long term interim storage. The containers are required to remain retrievable for centuries. One factor limiting their performance on this time scale is corrosion. The estimation of the metal thickness lost by dry oxidation over such long periods requires the construction of reliable models from short-time experimental data. Two complementary approaches for modelling dry oxidation have been considered. First, basic models following simple analytical laws from classical oxidation theories have been adjusted on the apparent activation energy of oxidation deduced from experimental data. Their extrapolation to long oxidation periods confirms that the expected damage due to dry oxidation could be small. Second, a numerical model able to take in consideration several mechanisms controlling the oxide scale growth is under development. Several preliminary results are presented. (authors)

  10. Modeling of the process of moisture loss during the storage of dried apricots.

    Science.gov (United States)

    Miranda, G; Berna, A; Bon, J; Mulet, A

    2011-10-01

    Moisture content is a reference parameter for dried food because the growth of most microorganisms is inhibited below certain water activity levels. In addition, it has a determining influence on the evolution of important parameters, such as color and flavor, and on other properties and deterioration reactions, such as texture, oxidation processes and nutritional value. During the storage of some dried fruits, moisture is produced due to Maillard reactions and exchanged with the surrounding environment through the packaging. The evolution of dried foods during their shelf life depends on the storage conditions. The aim of this study is to analyze the evolution of the moisture content in dried apricots packaged in different types of containers, namely glass and thermosealed polypropylene trays. The samples were stored at constant temperatures: 5, 15, 25 and 35 °C and were analyzed periodically over a period of 12 months. The sorption isotherms of apricots used in this study were also determined. In order to model how the moisture evolved, an empirical kinetic model was tested. This model considers both water transfer from the fruit and also water production as a result of the Maillard processes. The explained variance was higher than 95% in the samples stored in trays, which were thermosealed with film.

  11. Absence of storage effects on radiation damage after thermal neutron irradiation of dry rice seeds

    Energy Technology Data Exchange (ETDEWEB)

    Kowyama, Y. [Mie Univ., Tsu (Japan); Saito, M.; Kawase, T.

    1987-09-15

    Storage effects on dry rice seeds equilibrated to 6.8% moisture content were examined after irradiation with X-rays of 5, 10, 20 and 40 kR and with thermal neutrons of 2.1, 4.2, 6.3 and 8.4×10{sup 13}N{sub th}/cm{sup 2}. Reduction in root growth was estimated from dose response curves after storage periods of 1 hr to 21 days. The longer the storage period, the greater enhancement of radiation damages in X-irradiated seeds. There were two components in the storage effect, i. e., a rapid increase of radiosensitivity within the first 24 hr and a slow increase up to 21 days. An almost complete absence of a storage effect was observed after thermal neutron exposure, in spite of considerably high radioactivities of the induced nuclides, {sup 56}Mn, {sup 42}K and {sup 24}Na, which were detected from gamma-ray spectrometry of the irradiated seeds. The present results suggest that the contributions of gamma-rays from the activated nuclides and of inherent contaminating gamma-rays are little or negligible against the neutron-induced damage, and that the main radiobiological effects of thermal neutrons are ascribed to in situ radiations, i, e., heavy particles resulting from neutron-capture reaction of atom. A mechanism underlying the absence of storage effect after thermal neutron irradiation was briefly discussed on the basis of radical formation and decay. (author)

  12. Corrosion experiments on stainless steels used in dry storage canisters of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Ryskamp, J.M.; Adams, J.P.; Faw, E.M.; Anderson, P.A.

    1996-09-01

    Nonradioactive (cold) experiments have been set up in the Idaho Chemical Processing Plant (ICPP)-1634, and radioactive (hot) experiments have been set up in the Irradiated Fuel Storage Facility (IFSF) at ICPP. The objective of these experiments is to provide information on the interactions (corrosion) between the spent nuclear fuel currently stored at the ICPP and the dry storage canisters and containment materials in which this spent fuel will be stored for the next several decades. This information will be used to help select canister materials that will retain structural integrity over this period within economic, criticality, and other constraints. The two purposes for Dual Purpose Canisters (DPCs) are for interim storage of spent nuclear fuel and for shipment to a final geological repository. Information on how corrosion products, sediments, and degraded spent nuclear fuel may corrode DPCs will be required before the DPCs will be allowed to be shipped out of the State of Idaho. The information will also be required by the Nuclear Regulatory Commission (NRC) to support the licensing of DPCs. Stainless steels 304L and 316L are the most likely materials for dry interim storage canisters. Welded stainless steel coupons are used to represent the canisters in both hot and cold experiments.

  13. Use of filler materials to aid spent nuclear fuel dry storage

    International Nuclear Information System (INIS)

    Anderson, K.J.

    1981-09-01

    The use of filler materials (also known as stabilizer or encapsulating materials) was investigated in conjunction with the dry storage of irradiated light water reactor (LWR) fuel. The results of this investigation appear to be equally valid for the wet storage of fuel. The need for encapsulation and suitable techniques for closing was also investigated. Various materials were reviewed (including solids, liquids, and gases) which were assumed to fill the void areas within a storage can containing either intact or disassembled spent fuel. Materials were reviewed and compared on the basis of cost, thermal characteristics, and overall suitability in the proposed environment. A thermal analysis was conducted to yield maximum centerline and surface temperatures of a design basis fuel encapsulated within various filler materials. In general, air was found to be the most likely choice as a filler material for the dry storage of spent fuel. The choice of any other filler material would probably be based on a desire, or need, to maximize specific selection criteria, such as surface temperatures, criticality safety, or confinement

  14. Corrosion experiments on stainless steels used in dry storage canisters of spent nuclear fuel

    International Nuclear Information System (INIS)

    Ryskamp, J.M.; Adams, J.P.; Faw, E.M.; Anderson, P.A.

    1996-09-01

    Nonradioactive (cold) experiments have been set up in the Idaho Chemical Processing Plant (ICPP)-1634, and radioactive (hot) experiments have been set up in the Irradiated Fuel Storage Facility (IFSF) at ICPP. The objective of these experiments is to provide information on the interactions (corrosion) between the spent nuclear fuel currently stored at the ICPP and the dry storage canisters and containment materials in which this spent fuel will be stored for the next several decades. This information will be used to help select canister materials that will retain structural integrity over this period within economic, criticality, and other constraints. The two purposes for Dual Purpose Canisters (DPCs) are for interim storage of spent nuclear fuel and for shipment to a final geological repository. Information on how corrosion products, sediments, and degraded spent nuclear fuel may corrode DPCs will be required before the DPCs will be allowed to be shipped out of the State of Idaho. The information will also be required by the Nuclear Regulatory Commission (NRC) to support the licensing of DPCs. Stainless steels 304L and 316L are the most likely materials for dry interim storage canisters. Welded stainless steel coupons are used to represent the canisters in both hot and cold experiments

  15. Develop an piezoelectric sensing based on SHM system for nuclear dry storage system

    Science.gov (United States)

    Ma, Linlin; Lin, Bin; Sun, Xiaoyi; Howden, Stephen; Yu, Lingyu

    2016-04-01

    In US, there are over 1482 dry cask storage system (DCSS) in use storing 57,807 fuel assemblies. Monitoring is necessary to determine and predict the degradation state of the systems and structures. Therefore, nondestructive monitoring is in urgent need and must be integrated into the fuel cycle to quantify the "state of health" for the safe operation of nuclear power plants (NPP) and radioactive waste storage systems (RWSS). Innovative approaches are desired to evaluate the degradation and damage of used fuel containers under extended storage. Structural health monitoring (SHM) is an emerging technology that uses in-situ sensory system to perform rapid nondestructive detection of structural damage as well as long-term integrity monitoring. It has been extensively studied in aerospace engineering over the past two decades. This paper presents the development of a SHM and damage detection methodology based on piezoelectric sensors technologies for steel canisters in nuclear dry cask storage system. Durability and survivability of piezoelectric sensors under temperature influence are first investigated in this work by evaluating sensor capacitance and electromechanical admittance. Toward damage detection, the PES are configured in pitch catch setup to transmit and receive guided waves in plate-like structures. When the inspected structure has damage such as a surface defect, the incident guided waves will be reflected or scattered resulting in changes in the wave measurements. Sparse array algorithm is developed and implemented using multiple sensors to image the structure. The sparse array algorithm is also evaluated at elevated temperature.

  16. Proposal of a dry storage installation in Angra NPP for spent nuclear fuel

    International Nuclear Information System (INIS)

    Romanato, Luiz S.; Rzyski, Barbara M.

    2009-01-01

    When nuclear fuel is removed from a power reactor core after the depletion of efficiency in generating energy is called Spent Nuclear Fuel (SNF). After its withdrawal from the reactor core, SNF is temporarily stored in pools usually at the same site of the reactor. During this time, short-living radioactive elements and generated heat undergo decay until levels that allow removing the SNF from the pool and sending it for reprocessing or a temporary storage whether any of its final destinations has not yet been defined. It can be loaded in casks and disposed during years in a dry storage installations until be sent to a reprocessing plant or deep repositories. Before any decision, reprocessing or disposal, the SNF needs to be safely and efficiently isolated in one of many types of storages that exist around the world. Worldwide, the amount of SNF increases annually and in the next years this amount will be higher as a consequence of new Nuclear Power Plants (NPP) construction. In Brazil, that is about to construct the Angra 3 nuclear power reactor, a project about the final destination of the SNF is not yet ready. This paper presents a proposal for a dry storage installation in the Angra NPP site since it can be an initial solution for the Brazilian's SNF, until a final decision is taken. (author)

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

    International Nuclear Information System (INIS)

    Geoffroy, J.; Dobremelle, M.; Fabre, J.C.; Bonnet, C.

    1989-01-01

    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

  18. Probabilistic risk assessment of aircraft impact on a spent nuclear fuel dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Almomani, Belal, E-mail: balmomani@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Lee, Sanghoon, E-mail: shlee1222@kmu.ac.kr [Department of Mechanical and Automotive Engineering, Keimyung University, Dalgubeol-daero 1095, Dalseo-gu, Daegu (Korea, Republic of); Jang, Dongchan, E-mail: dongchan.jang@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Kang, Hyun Gook, E-mail: kangh6@rpi.edu [Department of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute, Troy, NY 12180 (United States)

    2017-01-15

    Highlights: • A new risk assessment frame is proposed for aircraft impact into an interim dry storage. • It uses event tree analysis, response-structural analysis, consequence analysis, and Monte Carlo simulation. • A case study of the proposed procedure is presented to illustrate the methodology’s application. - Abstract: This paper proposes a systematic risk evaluation framework for one of the most significant impact events on an interim dry storage facility, an aircraft crash, by using a probabilistic approach. A realistic case study that includes a specific cask model and selected impact conditions is performed to demonstrate the practical applicability of the proposed framework. An event tree analysis of an occurred aircraft crash that defines a set of impact conditions and storage cask response is constructed. The Monte-Carlo simulation is employed for the probabilistic approach in consideration of sources of uncertainty associated with the impact loads onto the internal storage casks. The parameters for representing uncertainties that are managed probabilistically include the aircraft impact velocity, the compressive strength of the reinforced concrete wall, the missile shape factor, and the facility wall thickness. Failure probabilities of the impacted wall and a single storage cask under direct mechanical impact load caused by the aircraft crash are estimated. A finite element analysis is applied to simulate the postulated direct engine impact load onto the cask body, and a source term analysis for associated releases of radioactive materials as well as an off-site consequence analysis are performed. Finally, conditional risk contribution calculations are represented by an event tree model. Case study results indicate that no severe risk is presented, as the radiological consequences do not exceed regulatory exposure limits to the public. This risk model can be used with any other representative detailed parameters and reference design concepts for

  19. Dry Cask Storage Characterization Project - Phase 1: CASTOR V/21 Cask Opening and Examination

    Energy Technology Data Exchange (ETDEWEB)

    Bare, Walter Claude; Ebner, Matthias Anthony; Torgerson, Laurence Dale

    2001-08-01

    This report documents visual examination and testing conducted in 1999 and early 2000 at the Idaho National Engineering and Environmental Laboratory (INEEL) on a Gesellschaft für Nuklear Service (GNS) CASTOR V/21 pressurized water reactor (PWR) spent fuel dry storage cask. The purpose of the examination and testing is to develop a technical basis for renewal of licenses and Certificates of Compliance for dry storage systems for spent nuclear fuel and high-level waste at independent spent fuel storage installation sites. The examination and testing was conducted to assess the condition of the cask internal and external surfaces, cask contents consisting of 21 Westinghouse PWR spent fuel assemblies from Dominion’s (formerly named Virginia Power) Surry Power Station and cask concrete storage pad. The assemblies have been continuously stored in the CASTOR cask since 1985. Cask exterior surface and selected fuel assembly temperatures, and cask surface gamma and neutron dose rates were measured. Cask external/internal surfaces, fuel basket components including accessible weldments, fuel assembly exteriors, and primary lid seals were visually examined. Selected fuel rods were removed from one fuel assembly, visually examined, and then shipped to Argonne National Laboratory for nondestructive, destructive, and mechanical examination. Cask interior crud samples and helium cover gas samples were collected and analyzed. The results of the examination and testing indicate the concrete storage pad, CASTOR V/21 cask, and cask contents exhibited sound structural and seal integrity and that long-term storage has not caused detectable degradation of the spent fuel cladding or the release of gaseous fission products between 1985 and 1999.

  20. Dry storage of MTR spent fuel from the Argentine radioisotope production reactor RA-3; Proyecto de compactado y reubicacion de los elementos combustibles quemados del RA-3 en el deposito de combustibles MTR del Centro Atomico Ezeiza

    Energy Technology Data Exchange (ETDEWEB)

    Di Marco, A; Gillaume, E J; Ruggirello, G; Zaweruchi, A [Comision Nacional de Energia Atomica, San Martin (Argentina). Unidad de Actividad Combustibles Nucleares

    1997-12-31

    The nuclear fuel elements of the RA-3 reactor consist in 19 rectangular fuel plates held in position by two lateral structural plates. The whole assembly is coupled to the lower nozzles that fits in the reactor core grid. The inner plates are 1.5 mm thick, 70.5 mm wide and 655 mm long and the outer plates are 100 mm longer. The fuel plates are formed by a core of an AI-U alloy co-laminated between two plates of Al. Enrichment is 90% {sup 235}U. After being extracted from the reactor, the fuel elements have been let to cool down in the reactor storage pool and finally moved to the storage facility. This facility is a grid of vertical underground channels connected by a piping system. The system is filled with processed and controlled water. At the present the storage capacity of the facility is near to be depleted and some indications of deterioration of the fuel elements has been detected. Due to the present status of the facility and the spent fuel stored there, a decision has been taken to proceed to modify the present underwater storage to dry storage. The project consist in: a) Decontamination and conditioning of the storage channels to prepare them for dry storage. b) Disassembly of the fuel elements in hot cells in order to can only the active fuel plates in an adequate tight canister. c) The remnant structural pieces will be treated as low level waste. (author). 10 figs.