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Din avgränsning ger 440 träffar.

• 2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents

  14 november 2017

  Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents 2017:20 Author: Lars Olof Jernkvist SSM 2017:20 SSM 2017:20 SSM:s perspektiv ... shändelser (RIA) i lättvattenreaktorer. I utbyte mot årliga bidrag till utvecklingen av SCANAIR har SSM tillgång till beräkningsprogrammet och kan utföra egna analyser av bränslebeteende under reaktivitetshän-...

  Innehållstyp: Dokument

• SSM Report 2014:59 TN part III-3 page 191-220

  06 november 2017

  7315 kB ... South Korea Technical Note 74; page 191-220 SSM 2014:59 191 Models in Section 6.4 Earthquake induced, ZFMA2, present day reverse stress field, DFN03v Figure A3-117. Spatial distribution ... 1 0.037 S h e a r d is p la c e m e n t (m ) TF/DZ trace length (m) WC1994 DS (Leonard 2010) SS (Leonard 2010) SCR (Leonard 2010) TF DZ Active EQ DZ, mean SSM 2014:59 192...

  Innehållstyp: Dokument

• SSM Report 2014:59 TN part III-2 page 163-190

  06 november 2017

  18109 kB ... Berlin, Germany 2) Seoul National University, Seoul, South Korea Technical Note 74; page 163-190 SSM 2014:59 163 Models in Section 6.2 Earthquake induced, ZFMWNW0809A, glacial induced stress at ... 1 0.121 S h e a r d is p la c e m e n t (m ) TF/DZ trace length (m) WC1994 DS (Leonard 2010) SS (Leonard 2010) SCR (Leonard 2010) TF DZ Active EQ DZ, mean SSM 2014:59 164...

  Innehållstyp: Dokument

• SSM Report 2014:59 TN part II page 61-142

  06 november 2017

  University, Seoul, South Korea Technical Note 74; page 61-142 SSM 2014:59 61 6. Modelling of target fracture responses to earthquakes on deformation zones 6.1. Earthquake at selected deformation ... deformation zones – present-day “most likely” reverse stress field – Horizontal section model The modelling cases in this Chapter do not include rock mass heating. Therefore, the modelling was performed without...

  Innehållstyp: Dokument

• SSM Report 2014:59 TN part I page -60

  06 november 2017

  Review Phase Authors: Jeoung Seok Yoon Ove Stephansson Ki-Bok Min SSM perspektiv Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen ... ett slutförvar för använt kärnbränsle och även inkapslingsanläggning. Som en del i granskningen ger SSM kon- sulter uppdrag för att inhämta information och göra expertbedömningar i avgränsade frågor. I...

  Innehållstyp: Dokument

• 2017:09 Evaluation of the Swedish participation in the Nordic Nuclear Safety Research (NKS) collaboration

  27 september 2017

  Authors: Hjalmar Eriksson August Olsson SSM 2017:09 SSM 2017:09 SSM perspective Background NKS is a Nordic collaboration promoting cooperation on nuclear safety and emergency preparedness research ... technical reports, exercises and scientific articles. Both radiation safety authorities, industries and research actors are engaged in NKS projects Objective This is a report on the evaluation of the Swedish...

  Innehållstyp: Dokument

• 2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik

  14 november 2017

  Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik 2017:12 Author: Lars Olof Jernkvist SSM 2017:12 SSM 2017:12 SSM perspective Background Loss of Coolant ... in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of active...

  Innehållstyp: Dokument

• SSM Report 2014:59 TN part III-1 page 143-162

  06 november 2017

  11709 kB ... Berlin, Germany 2) Seoul National University, Seoul, South Korea Technical Note 74; page 143-162 SSM 2014:59 143 APPENDIX 3 Result of all PFC modelling cases In this appendix, all ... -6.000 -5.000 -4.000 -3.000 -2.000 -1.000 0 -0.14 0.33 0.53 0.85 1.05 SSM 2014:59 144 Figure A3-2. Shear displacement of the TFs and DZs with respect to length, due to...

  Innehållstyp: Dokument

• 2017:12 Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik

  in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subsequent release of active ... 5 (see SSM report 2015:37). Objective This report describes the validation of the models against tests performed in Halden and in Studsvik, the latter commissioned by NRC. The objective for SSM in this...

  Innehållstyp: Publikationer

• 2017:36 Topical Peer Review 2017 Ageing Management Swedish National Assessment Report

  Executive summary The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years with the first starting in 2017. The ... topic for the first topical peer review is ageing management. The Swedish Radiation Safety Authority (SSM) by the provision of the act of nuclear activities (1984:3) can decide by injunction that licensees...

  Innehållstyp: Publikationer