Din avgränsning ger 280 träffar.
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1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy
A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is ... provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about 20 years. For cooling...
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 -
2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach
results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden ... objectives of the project are: 1) to investigate the possibility of initiation and growth of fractures in the cast-iron canisters under the mechanical loading conditions defined in the premises of canister...
Innehållstyp: Publikationer -
1992:3 Characterization of seismic ground motions for probabilistic safety analyses of nuclear facilities in Sweden. SUMMARY REPORT
In Scandinavia seismic activity is generally low. Only a few incidents have been registered in historic time, which might have damaged an industrial plant of today. The risk of a nuclear accident in Sweden ... resist a specified earthquake. For the older reactors no corresponding analyses or designs have been made initially. Their general design is robust.and was considered to provide enough safety with regard...
Innehållstyp: Publikationer -
2010:33 Lineament interpretation Short review and methodology
This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints ... viewpoints presented in the report are those of the author and do not necessarily coincide with those of the SSM. In the characterization of a site that may have potential for hosting a repository for spent...
Innehållstyp: Publikationer -
2010:23 On Decommissioning Costs of the Ranstad Site
A demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake ... undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in the context of Swedish as well as European environmental and health codes is...
Innehållstyp: Publikationer -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the ... states of the structural iron in montmorillonite, the dominant mineral in bentonite, have been shown to be sensitive to such irradiation in experimental studies using suspended bentonite. The change of the...
Innehållstyp: Publikationer -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are ... The pipe systems may contain the damage mechanisms fatigue and/or stress corrosion cracking. In the report, the results are presented for evaluating PRO-LOCA, version 4.1.9. The report contains a sensitivity...
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 -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay ... is located in Oskarshamn, Sweden. The Clab facility operates several linked underground storage pools which are expected to have a storage capacity of 11,000 tons. Figure 1 is a photo of one of the underground...
Innehållstyp: Publikationer