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Din avgränsning ger 33 träffar.

• 2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment

  (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered ... Engineered Barrier System (EBS) and spent fuel. This workshop concerns the assessment of the spent fuel performance and near-field radionuclide retardation mechanisms in the engineered barriers. This will...

  Innehållstyp: Publikationer

• 2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister

  The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long ... long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration tests at...

  Innehållstyp: Publikationer

• 2007:10 DECOVALEX-THMC - Task D

  Inspectorate, with participation of about 10 international organizations. The name DECOVALEX stands for DEvelopment of COupled models and their VALidation against Experiments. The general goal of this project ... coupled processes in geologic formations in support of the performance assessment for underground storage of radioactive waste. Three multi-year project stages of DECOVALEX have been completed in the past decade...

  Innehållstyp: Publikationer

• 2007:11 Review of Quality Assurance in SKBs Repository Research Experiments

  SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure ... post-closure phase. As a preparation for SR-Site SKB has recently produced the SRCan safety assessment, which is currently in review. The assessment of long-term safety is based on a broad range of experimental...

  Innehållstyp: Publikationer

• 2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases

  test cases” presents a common attempt by the authorities and the utilities to create a methodology and experience base for defence and analysis of dependent failures. The performed benchmark application ... is interpreted is of significant importance. Good features were found in all approaches. We should try to take them and develop the existing approaches into a harmonised direction. A next step could be...

  Innehållstyp: Publikationer

• 2007:03 Variability and Uncertainties of Key Hydrochemical Parameters for SKB Sites

  part of the site investigations conducted by the Swedish Nuclear Fuel and Waste Management Company (SKB) is the characterisation of groundwater chemical conditions in the deep bedrock environment where ... where a final repository for spent nuclear fuel is planned to be located. This work is currently in its final stages at the two candidate sites, Forsmark and Laxemar, and should be completed by the summer...

  Innehållstyp: Publikationer

• 2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod

  structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower ... without scram, and loss of coolant accidents (LOCA). Its experimental database covers boiling- and pressurized water reactor fuel rods with UO2 fuel up to rod burnups around 64 MWd/kgU. In FRAPTRAN-1.3, the...

  Innehållstyp: Publikationer

• 2007:29 Intercomparison of Cement Solid-Solution Models

  the geological storage of radioactive waste incorporate cement based materials, which act to provide a chemical barrier, impede groundwater flow or provide structural integrity of the underground structures ... behaviour of these materials when modelling scenarios for the potential release and migration of radionuclides. In the presence of invasive groundwater, the chemical and physical properties of cement, such...

  Innehållstyp: Publikationer

• 2007:08 DECOVALEX-THMC - Task B

  contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models ... simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other loading conditions with the intention of establishing the common...

  Innehållstyp: Publikationer

• 2008:30 A model for fission gas release from mixed oxide nuclear fuel

  the 1960's. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors ... can be seen as a method to more efficiently use the natural uranium since most isotopes in natural uranium are the Pu-producing U-238. In fact, programs for using MOX were developed in the 1970's to meet...

  Innehållstyp: Publikationer