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Din avgränsning ger 495 träffar.

• 2007:05 Development of an Input Model to MELCOR 1.8.5 for Oskarshamn 3 BWR

  An input model has been prepared for the Oskarshamn 3 rector. Demonstrations calculations, at current nominal operating conditions in Oskarshamn 3 for 3300 MW thermal power, were performed for three cases: (1) initial, steady-state conditions, (2) total loss of AC power and (3) large steam line LOCA. The results are presented in the report. 200 Lars Nilsson SKI English An input model has been...

  Innehållstyp: Publikationer

• 2007:33 Analys av mänsklig tillförlitlighet HRA-begreppets tillämpbarhet vid revisionsavställning

  Analyser av mänsklig tillförlitlighet, Human Reliability Analysis (HRA) har använts under en längre tid i kärnkraftverkens probabilistiska säkerhetsanalyser. SKI har nyligen genomfört en utredning om befintliga metoder inom området HRA (litteraturstudie) och hur dessa metoder används av tillståndshavarna för de svenska kärnkraftverken...

  Innehållstyp: Publikationer

• 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 shown that, 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...

  Innehållstyp: Publikationer

• 2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository

  Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...

  Innehållstyp: Publikationer

• 2019:08 Recent Research on EMF and Health Risk, Thirteenth report from SSM’s Scientific Council on Electromagnetic Fields, 2018

  SSM perspective Background The Swedish Radiation Safety Authority’s (SSM) Scientific Council on Electromagnetic Fields monitors current research on potential health risks with a correlation to exposure to electromagnetic fields and provides the Authority with advice on assessing possible health risks. The Council gives guidance when the Authority must give an opinion on policy matters when...

  Innehållstyp: Publikationer

• 2019:06 The Changing Landscape of Non-proliferation and the EU

  Background Maintaining competence and knowledge within the nuclear non-proliferation area is a necessity for Sweden to keep its international commitments of peaceful use of all nuclear material. As part of this work the Swedish Radiation Safety Authority (SSM) made a call for research proposals related to Non-Proliferation for projects focused on the interplay between national and...

  Innehållstyp: Publikationer

• 2013:28 Brine intrusion by upconing for a high-level nuclear waste repository at Forsmark. Scoping calculations

  The objective of this study is to evaluate the possibility of salt-water migration to the spent nuclear repository. This objective is motivated by the adverse impacts of water with too high salinity entering the repository and by the uncertainty of the relevant hydraulic and hydrogeochemical conditions at the Forsmark site at great depths. To analyse density dependent flow and salt transport...

  Innehållstyp: Publikationer

• 2012:71 Identification of Brittle Deformation Zones and Weakness Zones

  In preparation for the review of Swedish Nuclear Fuel and Waste Management Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority (SSM) is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at...

  Innehållstyp: Publikationer

• 2015:28 Utvärdering av materialdata för befintliga betongkonstruktioner - med inriktning på verifiering av förankringar vid kärntekniska anläggningar

  Bakgrund I de Svenska kärnkraftverken finns ett stort antal fästplattor som är ingjutna alternativt eftermonterade. Fästplattan består av en förankringsplatta med tillhörande betonginfästning. Kapaciteten för flera av de viktigare brottmoderna för betonginfästningar styrs av hållfastheten hos omgivande betong. Betongens hållfasthet...

  Innehållstyp: Publikationer

• 2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load

  Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...

  Innehållstyp: Publikationer