Din avgränsning ger 301 träffar.
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2007:07 DECOVALEX-THMC Project - Task A
This report presents the definition of the first phase, Task A-1, of the Task A of the international DECOVALEX project. The task is a working example of how interaction between THMC modelling and SA analysis could be performed. Starting with the technical definition of the Task A, the report presents the results of preliminary THM calculations with a purpose of an initial appreciation of the...
Innehållstyp: Publikationer -
2007:09 DECOVALEX-THMC - Task C
This report describes the results of Task C1 of the international DECOVALEX– THMC project devoted to Excavation Damage Zone (EDZ) in argillaceous rock at the Tournemire site in France. Task C of the project is aimed to understand the physical phenomena induced by excavation in the argillaceous rock. The task is to develop adequate numerical models for interpretation of observed damaged zones...
Innehållstyp: Publikationer -
2007:10 DECOVALEX-THMC - Task D
The DECOVALEX project is an international cooperative project initiated by SKI, the Swedish Nuclear Power 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 is to encourage multidisciplinary interactive and cooperative research on...
Innehållstyp: Publikationer -
2018:25 UO2 fuel oxidation and fission gas release
Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that has been the main question of several research projects is the fragmentation of fuel pellets during abnormal heat up. In this project the oxidation of UO2 is scrutinized and its effect on pellet fragmentation, fission gas release and damage of fuel rods has been...
Innehållstyp: Publikationer -
1986:12 Chernobyl - its impact on Sweden
In case of a radiological emergency in Sweden, the Swedish National Institute of Radiation Protection (SSI) has the responsibility of organ1z1ng a special task force with experts both from SSI and from other authorities. Reports of increased radiation l evels reached SSI around 10 am on April 28, 1986, and the task force convened at 1030 am. A large number of measurements were made all over...
Innehållstyp: Publikationer -
2020:13 Core data Research at Uppsala University
SSM perspective Background This project is to support a research group at Uppsala University in the research field of nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data libraries are used in different applications such as, nuclear technology,...
Innehållstyp: Publikationer -
2020:02 Models for axial gas flow and mixing in LWR fuel rods
SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow to the plenum volume at the top of the fuel rod. In high burnup fuel, this axial flow to the...
Innehållstyp: Publikationer -
2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint
SSM perspective Background Leak-before-break (LBB) piping assessments have shown that piping systems can withstand long through-wall cracks before pipe rupture is expected. This is somewhat because pipe ends are restrained. In LBB assessments analyses are often performed for a pipe segment uncoupled from the piping system, as pipe ends are assumed unrestrained. This assumption is conservative...
Innehållstyp: Publikationer -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its 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 heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Innehållstyp: Publikationer -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered 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 repository. The redox states of the structural iron in montmorillonite, the dominant...
Innehållstyp: Publikationer