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          Spent Fuel Performance Assessment and Research (SPAR III)

          Closed for Proposals

          Project Type

          Coordinated Research Project

          Project Code

          T13013

          CRP

          1629

          Approved Date

          2008/12/10

          Project Status

          Closed

          Start Date

          2009/11/06

          Expected End Date

          2014/11/06

          Completed Date

          2014/09/30

          Description

          SPAR III is a continuation of the SPAR II CRP dealing with research of spent fuel and storage materials behaviour over long term spent fuel storage (100 years and potentially more).Programs carried out so far (BEFAST, SPAR I and II) have identified some potential deterioration mechanisms of spent fuel elements that required detailed investigation. Investigations of these mechanisms indicate unlikely impact of most of them on spent fuel integrity over storage periods. There are still impacts of some deterioration mechanisms that have to be investigated over long time periods (i.e. hydrogen effects on fuel elements) and countries that participated in SPAR II continue this research. In addition, behaviour and impact on these mechanisms under transportation and some extreme conditions need to be investigated. Surveillance and monitoring results of spent fuel in storage are important inputs in assessing spent fuel performance in storage. The long term objective of spent fuel integrity is to keep all future spent fuel management options open.

          Objectives

          Development of a technical knowledge base on long term storage of power reactor spent fuel through evaluation of operating experience and research by participating member states.

          Specific Objectives

          Collection and exchange of relevant experience of spent fuel storage and the impact on associated spent fuel management activities in the participating countries

          Creating synergy among research projects of the participating member states

          Developing capability to assess the impact of potential deterioration mechanisms on fuel and spent fuel storage components

          Facilitate transfer of knowledge by documenting technical basis for spent fuel storage

          Fuel and materials performance evaluation under wet and dry storage, and assessment of impact of interim storage on associated spent fuel management activities (like handling and transport)

          Surveillance and monitoring programmes of spent fuel storage facilities as one of the means to evaluate spent fuel performance during storage

          Impact

          Knowledge Base
          The accumulated reporting of the IAEA’s BEFAST and SPAR CRPs now exceeds 30 years. In the context of 100+ years storage it is important that this knowledge base is continued to be updated and on on-going spent fuel and system performance reported.
          Spent Fuel Performance
          For zirconium and stainless steel based LWR clad spent fuels there is now >50 years wet storage and >30 years dry storage experience. Performance in storage remains excellent with no generic failure mechanism identified or experienced. In the case of stainless clad AGR spent fuels there is >30 years of wet storage experience. Storage performance is good provided the fuel is stored in the presence of corrosion inhibitor. For MAGNOX spent fuel, magnesium alloy clad there is >50 years’ experience in handling and storage. The tendency is only to store for relative short periods of time in wet storage, but the fuel will remain intact for longer periods provided optimum storage chemistry is maintained.
          Spent Fuel Degradation
          A considerable number of studies on hydrogen behaviour in zirconium based clad material have been undertaken during this phase of the SPAR project. Whilst studies using empty clad tubes have improved the understanding of hydrogen behaviour in zirconium based clad material, the properties associated with the presence of fuel may be different. A gap in this area remains in establishing experiments under actual storage conditions.
          Impact of Interim Storage on Associated Spent Fuel Management Activities
          Improving the knowledge base on spent fuel behaviour for retrieval and transport situations has been investigated. The amount of fuel material released upon impact appears to be independent of fuel burnup, test method, is localized to the area of rupture and has been found to be <2 pellets worth of material for all fuel types tested. The studies have enabled establishing reference conditions for safety assessments.
          Materials Performance in Storage Systems
          Knowledge of the long-term performance of materials used in spent fuel storage systems is required for continued operations and for storage system relicensing. A number of studies on the behaviour of materials have continued or been initiated during this phase of the SPAR project. In some areas, such as the influence of stress corrosion cracking (SCC) on dry storage canisters in marine environment, studies are still ongoing. In other areas, for example metal seals, the experience to date and on-going long-term studies have not established limiting factors for their continued use.
          Issues Related to Extended Storage of Spent Fuel
          In the very long-term, helium generation from a-decay and the accumulation of helium may become an important mechanism in fuel matrix evolution. Although there remains unknowns in relation to gas retention by the fuel matrix, bulk pellet swelling or release mechanisms to the free volume, even where all the gas generated in the first 300 year of UO2 spent fuel storage is released, there is a negligible effect on cladding stress during storage. More attention has to be devoted to spent MOX fuel behaviour.
          Way Forward
          Continued spent fuel storage and future transitions from one phase of the back-end of the nuclear fuel cycle to the next require that the operational experience and research results to be reported and disseminated to the Member States for input to continued operations safety assessments and the licensing of new facilities. In this respect field experience needs to be collected and reported; especially from the deployment of new technology.

          Relevance

          Spent fuel management has always been one of the most important stages in the nuclear fuel cycle, and stands among the most vital problems common to all Member States with nuclear reactors. In order to demonstrate safety over these long time periods a good understanding of the processes that might cause deterioration of the system are needed. The CRP wholly supports providing this understanding through reporting on-going behaviour of both spent fuel and the storage system. The major players in the CRP have now been storing spent fuel for decades and sharing this accumulated knowledge is essential both for existing operators and to new comers. In addition the CRP reports the latest R&D findings and thinking related to spent fuel storage and storage system performance.

          CRP Publications

          Argentina/CNEA
          Paper in scientific journal
          2014
          VIZCAINO, P., SANTISTEBAN, J.R., VICENTE-ALVAREZ, M.A., BANCHIK, A.D., ALMER, J., ‘Effect of crystallite orientation and external stress on hydride precipitation and dissolution in Zr2.5%Nb’, Journal of Nuclear Materials, Vol. 447, Issues 1–3, 82–93, (2014).
          Japan/CRIEPI
          Paper in scientific journal
          2013
          ETO, S., TANI, J., SHIRAI, K., et al., “Measurement of concentration of chlorine attached to a stainless steel canister material using laser induced breakdown spectroscopy”, Spectrochimica Acta part B, 87, 74—80, Elsevier, London, (2013).
          Japan/JNES
          Conference proceedings
          2013
          HIROSE, T., OZAWA, M., MIURA, H., BABA, T., KAMIMURA, K., “Research on Integrity of High Burnup Spent Fuel under Long Term Dry Storage and Transport,” OECD/NEA International Workshop on Safety of Long Term Interim Storage Facilities, Munich, Germany, May, (2013).
          USA/NRC
          Paper in scientific journal
          2013
          BILLONE, M.C., BURTSEVA, T.A., EINZIGER, R.E., “Ductile-to-brittle transition temperature for high burnup cladding alloys exposed to simulated drying—storage conditions”, Journal of Nuclear Materials, 433, 431—448, (2013).
          USA/NRC
          Conference Proceedings
          2012
          GONZALEZ, F., BAJWA, C., EASTON, E., EINZIGER, R., YANG, J., HNETKOVSKY, E., “Spent Nuclear Fuel Transportation Package Seals in Beyond Design Basis Temperature Excursions” in Proceedings of the ASME 2012 Pressure Vessels & Piping Division Conference-PVP2012, July 15 — 19, Toronto, Ontario, Canada, (2012).
          USA/NRC
          Technical Report
          2013
          MILLER, L., et.al., Overview of Vacuum Drying Methods and Factors Affecting the Quantity of Residual Water After Drying – Public Version, U.S. Nuclear Regulatory Commission Contract No. NRC–02–07–006, ML13192A125, (2013).
          USA/NRC
          Conference Proceedings
          2013
          WANG, J-A., WANG, H., BEVARD, B.B., HOWARD, R.L., FLANAGAN, M.E., “Reversible Bending Fatigue Test System for Investigating Vibration Integrity of Spent Nuclear Fuel during Transportation’, Proceedings of the 17th International Symposium on the Packaging and Transportation of Radioactive Materials - PATRAM 2013, August 18 — 23, San Francisco, CA, USA, (2013).
          UK/Sellafield Ltd.
          Conference proceedings
          (2010 - awaiting publication)
          STANDRING P. N., HANDS B. J., MORGAN S., BROOKS A., Development of an alternative corrosion inhibitor for the storage of advanced gas cooled reactor fuel, In Press Proc. International Conference on Management of Spent Fuel from Nuclear Power Reactors, 31 May – 4 June, Vienna, Austria (2010).
          USA/NRC
          Conference Proceedings
          2012
          AHN, T., OBERSON, G., DEPAULA, S., Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel for Dry Storage of Spent Nuclear Fuel, PRiME 2012, The Electrochemical Society, Honolulu, Hawaii, October 7 – 12, (2012).
          Argentina/CNEA
          Paper in scientific journal
          2012
          VICENTE-ALVAREZ, M.A., SANTISTEBAN, J.R., VIZCAINO, P., FLORES, A.V., BANCHIK, A.D., ALMER, J., ‘Hydride reorientation in Zr2.5%Nb studied by synchrotron X-ray diffraction’ Acta Materials, Vol. 60 Issue 20, 6892–6906, (2012).
          Japan/CRIEPI
          Conference proceedings
          2012
          WATARU, M., et al., “Long-term Containment Performance Test of Metal Cask for Spent Nuclear Fuel Storage”, PSAM, 25-29 June, 2012, Helsinki, Finland, (2012).
          USA/EPRI
          Technical Report
          2010
          ELECTRIC POWER RESEARCH INSTITUTE, Transportation of Commercial Spent Nuclear Fuel, EPRI, Palo Alto, CA, EPRI 1016637, (2010).
          USA/EPRI
          Technical Report
          2013
          ELECTRIC POWER RESEARCH INSTITUTE, Failure Modes and Effects Analysis (FMEA) of Welded Stainless Steel Canisters for Dry Cask Storage Systems, EPRI, Palo Alto, CA, EPRI 3002000815, (2013).
          Spain/ENRESA
          Conference proceedings
          2013
          TORRES, E., RUIZ-HERVíAS, J., MARTIN-RENGEL, M.A., Drop-weight ring compression test for evaluating the mechanical behaviour of fuel rods under impact conditions. PATRAM 2013, 18—23 August, San Francisco, USA, (2013).
          USA/NRC
          Technical Report
          2013
          MILLER, L., et.al, Vacuum Drying Test Plan - Public Version, U.S. Nuclear Regulatory Commission, Contract No. NRC–02–07–C–006, ML13192AA127, (2013).
          USA/EPRI
          Technical Report
          2011
          ELECTRIC POWER RESEARCH INSTITUTE, Benchmarks for Quantifying Fuel Reactivity Depletion Uncertainty, EPRI, Palo Alto, CA, EPRI 1022909, (2011).
          Korea Republic of/KAERI
          Conference proceedings
          2012
          KIM, Y., KIM, J., KOOK, D., KIM, Y., “Effects of hoop stress on the hydride reorientation in spent nuclear fuel cladding”, Trans. Of Korean Nuclear Society Autumn meeting, Gyeongju, Korea, October 25—26, (2012).
          Japan/JNES
          Conference proceedings
          2010
          KAMIMURA, K., et. al., “Integrity Criteria of Spent Fuel for Dry Storage in Japan”, International Seminar on Spent Fuel Storage (ISSF) 2010, Central Research Institute of Electric Power Industry, 15—17 November, Tokyo, Japan, (2010).
          EC JRC-ITU
          Conference proceedings
          2013
          AHN, T., RONDINELLA, V.V., WISS, T., Potential stress on cladding imposed by the matrix swelling from alpha decay in high burnup spent nuclear fuel, Proc. 14th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, New Mexico, April 28—May 2, Paper 6830, (2013).
          Argentina/CNEA
          Paper in scientific journal
          2012
          VICENTE-ALVAREZ, M.A., SANTISTEBAN, J.R., VIZCAINO, P., FLORES, A.V., BANCHIK, A.D., ALMER, J., ‘Hydride reorientation in Zr2.5%Nb studied by synchrotron X-ray diffraction’, Acta Materials, Vol. 60 Issue 20, 6892–6906, (2012).
          Argentina/CNEA
          Paper in scientific journal
          2011
          VIZCAíNO, P., FLORES, A.V., BOZZANO, P.B., BANCHIK, A.D., VERSACI, R.A., RíOS, R.O., “Hydrogen solubility and microstructure changes in zircaloy-4 due to neutron irradiation”, Journal of ASTM International, Vol. 8, No 1, Paper ID JAI102949, West Conshohocken, Pennsylvania, (2011).
          USA/NRC
          Conference Proceedings
          2013
          OBERSON, G., et.al., U.S. NRC Sponsored Research on Stress Corrosion Cracking Susceptibility of Dry Storage Canister Materials in Marine Environments, 2013 Waste Management Symposium, February 24— 28, Phoenix, AZ, (2013).
          USA/EPRI
          Technical Report
          2012
          ELECTRIC POWER RESEARCH INSTITUTE, Extended Storage Collaboration Program International Perspectives on Technical Gaps Associated with Extended Storage and Transportation of Used Nuclear Fuel, EPRI, Palo Alto, CA, EPRI 1026481, (2012).
          USA/NRC
          Conference Proceedings
          2012
          GONZALEZ, F., BAJWA, C., EASTON, E., EINZIGER, R., YANG, J., HNETKOVSKY, E., “Transportation Package Seal Performance in Beyond Design Basis Thermal Exposures”,– in Proc. Waste management 2012 Confer., Phoenix, AZ, paper 12472, (2012).
          USA/NRC
          Technical Report
          2010
          CASERES, L., MINTZ, T.S., Atmospheric Stress Corrosion Cracking Susceptibility of Welded and Unwelded 304, 304L, and 316L Austenitic Stainless Steels Commonly Used for Dry Cask Storage Containers Exposed to Marine Environments, NUREG/CR-7030, (2010).
          EC JRC-ITU
          Conference proceedings
          2011
          RONDINELLA, V.V., WISS, T., MAUGERI, E., COLLE, J-Y., Effects of helium build-up on nuclear fuel evolution during storage, Proc. 12th International High-Level Radioactive Waste Management Conference (IHLRWMC), Albuquerque, New Mexico, Apr 10—14, paper 3458, (2011).
          EC JRC-ITU
          Conference proceedings
          2012
          RONDINELLA, V.V., WISS, T., PAPAIOANNOU, D., NASYROW, R., Studies on nuclear fuel evolution during storage and testing of used fuel response to impact loadings, PSAM11-ESREL 2012, June 25-29, 2012, Helsinki; Vol. 1, 3171-3179, IAPSAM & ESRA, ISBN: 978-1-62276-436-5, (2012).
          Argentina/CNEA
          Paper in scientific journal
          2012
          SANTISTEBAN, J.R., VICENTE-ALVAREZ, M.A., VIZCAINO, P., BANCHIK, A.D., VOGEL, S.C., TREMSIN, A.S., VALLERGA, J.V., MCPHATE, J.B., LEHMANN, E., KOCKELMANN, W., ‘Texture imaging of zirconium based components by total neutron cross-section experiments’ Journal of Nuclear Materials, Vol. 425, Issues 1–3, 218–227, (2012).
          USA/NRC
          Technical Report
          2012
          JUNG, H., et.al. Extended Storage and Transportation: Evaluation of Drying Adequacy, U.S. Nuclear Regulatory Commission Contract NRC–02–07–006, ML13169A039, (2012).
          Spain/ENRESA
          Ph.D thesis
          2009
          MARTIN-RENGEL, M.A., Integridad estructural de vainas de combustible nuclear en condiciones de almacenamiento temporal en seco, PhD thesis, Universidad Politécnica de Madrid, ENRESA technical publication 05-2010 (in spanish), (2009).
          France/UK (AREVA TN/INS)
          Conference proceedings
          2011
          ZEACHANDIRIN, A., DALLONGEVILLE, M., PURCELL, P.C., CORY, A., “AREVA TN and INS: Description of Fuel Integrity Project methodology principles”, Packaging, Transport, Storage & Security of Radioactive Material (RAMTRANS), 22, 4, (2011).
          USA/NRC
          Technical Report
          2011
          YANG, J., HNETKOVSKY, E., “Performance of Metal and Polymeric O-Ring Seals in Beyond-Design-Basis Temperature Excursions”, NUREG/CR-7115, (2011).
          Japan/JNES
          Conference proceedings
          2013
          OZAWA, M., HIROSE, T., MIURA, H., BABA, T., KAMIMURA, K., AOMI, M., YASUDA, T., MURAKAMI, T.K., SHINOHARA, Y., Fuel Rod Mechanical Performance Under Dynamic Load Condition on High Burn-up Spent Fuel of BWR and PWR, PATRAM 2013, 18—23 August, San Francisco, USA, (2013).
          USA/NRC
          Paper in scientific journal
          2013
          EINZIGER, R., “An Aging Management Plan for Spent Fuel Storage and Transportation”, Radwaste Solutions, Vol. 20, No. 1, p. 38, (2013).
          Japan/CRIEPI
          Paper in scientific journal
          2014
          ETO, S., MIURA, Y., TANI, J., et al., “Effect of residual stress induced by pulsed-laser irradiation on initiation of chloride stress corrosion cracking in stainless steel”, Mat. Sci. Eng. A-Struct., 590, 433—439, (2014).
          Japan/CRIEPI
          Conference proceedings
          2012
          SHIRAI, K., TANI, J., GOTOH, M., WATARU, M., SCC Evaluation of Multi-Purpose Canister in Long Term Storage, in Proceedings of PSAM 11, 25—29 June, 2012, Helsinki, Finland, ISBN: 9781622764365, Curran Associates, (2012).
          Japan/JNES
          Conference proceedings
          2012
          HIROSE, T., OZAWA, M., MIURA, H., BABA, T., KAMIMURA, K., et al. “Dynamic Load Impact Tests on High Burnup Spent Fuel Rods of BWR and PWR”, NuMat 2012: the Nuclear Materials conference, Osaka, Japan, 22—25 October, (2012).

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