Din avgränsning ger 427 träffar.
-
2019:20 Assessment of structures subject to concrete pathologies (ASCET), phase 3
SSM perspective Background ASCET is an international research project initiated by WGIAGE1 OECD2 / NEA3. WGIAGE Concrete subgroup is a working group within the OECD / NEA whose task is to address issues concerning the maintenance of the integrity of concrete structures, proposals for general principles to optimally handle the challenges of integrity, especially with regard to ageing of...
Innehållstyp: Publikationer -
2019:23 Participation in the European Committee for Standardization's workshop regarding civil structures
SSM perspective Background During the period 2014-2018, a CEN1 workshop (Phase 2 Prospective Group 3 civil works) have been carried out. The aim of the workshop is to provide a base founded on the French standard in order to be able to establish a possible future European standard for the design of civil structures at nuclear power plants. The workshop has identied which additional...
Innehållstyp: Publikationer -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...
Innehållstyp: Publikationer -
2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment
The Swedish Radiation Safety Authority (SSM) reviews and follows associated research related to the Swedish Nuclear Fuel Company’s (SKB) work with establishing a repository for spent nuclear fuel and an encapsulation facility.
Innehållstyp: Publikationer -
2016:28 Fatigue fracture surface characterization and investigation
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to examine the obtained fatigue cracks with an optical microscope. Objective The present study performs a fractographical examination of the obtained fatigue cracks with the aim of determine where...
Innehållstyp: Publikationer -
2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems
The Swedish Radiation Safety Authority’s (SSM) experience is that there is a need to develop evaluation methods in parallel with the development of control rooms in conjunction with construction modifications and other changes. This includes more indepth analysis of the methods used today. Another aspect is that conventional methods of evaluating control rooms and issues need to be...
Innehållstyp: Publikationer -
2016:26 Ensemble for deterministic sampling with positive weights
The aim of this project is to find a reliable method for determining an ensemble for Deterministic Sampling with only positive weights. This report is intended to work as a presentation of the project, as well as to work as a beginner’s guide to DS. In the report several methods for generating DS ensembles are presented, which can encode up to four moments and represent any kind of...
Innehållstyp: Publikationer -
2016:13 Spännarmerade betongkonstruktioner vid kärntekniska anläggningar
Projektet omfattar en litteraturstudie och inventering av byggteknik, dimensionering, degradering och inspektionsmetoder för spännkabelsystem i reaktorinneslutningar och bassängkonstruktioner. Kunskap om spännkabelsystemen är av stor betydelse för bedömning av konstruktionernas täthet och uppfyllande av gällande säkerhetskrav. Patrick Anderson...
Innehållstyp: Publikationer -
2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents
In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...
Innehållstyp: Publikationer -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have 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 analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
Innehållstyp: Publikationer