Filtered generated 395 hits.
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2017:29 Evaluation of the simulation software CIVA for qualification purpose
Background Modeling is an important tool within NDT, partly to develop and optimize testing technologies, but also within the Qualification Body’s activities to assess technical verifications and perform parameter studies. SSM has supported university research in the area for many years and, among other things, in the development of a software for ultrasound modeling. In addition, the...
Content type: Publications -
2017:16 Stress intensity factor solutions for circumferential cracks in cylindrical bars under axisymmetric loading and global bending
Background The case of a circumferential crack in a cylindrical bar has not been available in the ProSACC code. The need for such a geometry, especially considering nonlinear axisymmetric loading and global bending, has motivated the development of new stress intensity factor solutions, also known as K-solutions. These new K-solutions will be available in ISAAC, the successor to ProSACC.
Content type: Publications -
2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling
SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs...
Content type: Publications -
2024:14 Residual stress distributions in nickel-based dissimilar metal pipe welds
SSM perspective This report concerns a study which has been conducted for the Swedish Radiation Safety Authority, SSM. The conclusions and viewpoints presented in the report are those of the author/authors and do not necessarily coincide with those of the SSM. Abstract It is common for nickel-base materials to be used as filler metals in the welding of dissimilar metal welds. Dissimilar metal...
Content type: Publications -
2021:05 Cladding tube rupture under LOCA: Data and models for rupture opening size
SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that is currently being studied in several research projects is the risk of release of fragmented fuel into the primary coolant in case of an accident. This risk depends on complex conditions were one is the possibility and size of a rupture of the fuel rod...
Content type: Publications -
2019:09 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Decommissioning of the nuclear reactor Ågesta in Sweden.
Content type: Publications -
2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants
Prof. István Furó, Dr. Payam Pourmand, Dr. Pavel Yushmanov SSM English...
Content type: Publications -
2013:35 Technical Note, Rock Mechanics – Confidence of SKB’s models for predicting the occurrence of a damage zone around the excavations – Main Review Phase
This assignment, performed at Southwest Research Institute, focusses on evaluating SKB’s assessment of potential occurrence of damaged rock zones (also referred to as excavation-damaged zone or EDZ) around underground excavations at the site. This report presents the authors’ evaluation of SKB’s assessment in the specific area based on questions raised by SSM. The evaluation includes...
Content type: Publications -
2012:53 Technical Note, Review of Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site – Initial Review Phase
SRK Consulting (UK) Limited (SRK) has reviewed the Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site in Sweden. The review assignment is part of a Swedish Radiation Safety Authority (SSM) Initial Review Phase. The review was carried out by David Saiang (PhD) on behalf of SRK. Therefore some of the views expressed in the...
Content type: Publications -
2012:48 Technical Note, Use of Solubility Limits in the SR-Site Safety Assessment
In a radioactive waste disposal environment, in some potential situations (scenarios) a disposed canister containing spent fuel may be breached and the fuel may come into contact with groundwater. The concentration of a radioactive element such as uranium may rise to a level where the solution is saturated. No more of the radioactive element may dissolve and a precipitated solid may be formed.
Content type: Publications