Showing 1402 hits for ””
-
2022:04 Warm Pre-Stressing mechanisms
SSM perspective Background Swedish nuclear power plants (NPP) were originally designed and analyzed with an assumed operating period of approximately 40 years. As Swedish NPPs reach their original technical design life the safety of the additional operating time has to be verified. With increased operating time, the shift in the fracture toughness curve of the reactor pressure vessel (RPV)...
Content type: Publications -
2022:09 Assessment of modelling approaches for axial gas flow inside LWR fuel rods
SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. The development and administration...
Content type: Publications -
2002:22 Review of data types for the SKB site investigation programme
SKB is currently undertaking a detailed site investigation programme (SIP) to characterise the geology and surface ecosystems in areas around potential sites for a planned repository for spent nuclear fuel. This report reviews site specific and generic data types needed to characterise biosphere processes relevant to the evaluation of long-term radiological safety in the context of assessments...
Content type: Publications -
2002:18 A Review of Models for Dose Assessment Employed by SKB in the Renewed Safety Assessment for SFR 1
This document provides a critical review, on behalf of SSI, of the models employed by the Swedish Nuclear Fuel and Waste Management Co (SKB) for dose assessment in the renewed safety assessment for the final repository for radioactive operational waste (SFR 1) in Forsmark, Sweden. The main objective of the review is to examine the models used by SKB for radiological dose assessment in a series...
Content type: Publications -
2022:14 Weld residual stress and strain measurements on a mock-up with single layer strip cladding common in reactor pressure vessels
Summary Residual stress and strain measurements were performed on a mock-up consisting of a 160 mm thick low-alloy ferritic steel plate of type SA-508 Class 3 with a single layer weld deposited strip cladding of austenitic stainless steel E308L. The cladding was manufactured with submerged arc strip welding adapted to a procedure used for reactor pressure vessels in the 1970s. Comprehensive...
Content type: Publications -
2002:17 Review of Project SAFE: Comments on biosphere conceptual model description and risk assessment methodology
The Swedish Nuclear Fuel and Waste Management Company’s (SKB’s) most recent assessment of the safety of the Forsmark repository for low-level and intermediatelevel waste (Project SAFE) is currently undergoing review by the Swedish regulators. As part of its review, the Swedish Radiation Protection Institute (SSI) identified that two components of SAFE require more detailed review: (i) the...
Content type: Publications -
2022:11 Kingdom of Sweden IRRS ARM Summary Report 2022
The IAEA Integrated Regulatory Review Service Mission to Sweden in November 2022...
Content type: Publications -
2002:23 Validation of dose calculation
This report describes a validation of the computer codes RESRAD-RECYCLE and CERISE, which are used to estimate radiation doses due to the recycling of scrap metal. Calculated external radiation doses to individuals are compared with measured data from different steps of the processing of slightly contaminated material, mainly in Studsvik, Sweden. Shankar Menon, Christine Brun-Yaba, Charley...
Content type: Publications -
2002:20 Expert Opinion in SR 97 and the SKI/SSI Joint Review of SR 97
The role of sensitivity and uncertainty analyses for radioactive waste disposal assessments is reviewed. The report covers a description of the these concepts were applied in the authorities’ review of the safety report SR 97. Stephen Hora SSI English The role of sensitivity and uncertainty analyses for radioactive waste disposal assessments is reviewed. The report covers a description of the...
Content type: Publications -
2002:19 Expert Judgement Elicitation
The report describes a trial expert panel elicitation with 4 experts in the field of radioecology. Stephen Hora and Mikael Jensen SSI English The report describes a trial expert panel elicitation with 4 experts in the field of radioecology.
Content type: Publications