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Din avgränsning ger 85 träffar.

• 2004:09 Low Temperature (320°C and 340°C) Creep Crack Growth in Low Alloy Reactor Pressure Vessel Steel

  01 januari 2004

  the CCG behaviour and to examine the effects of microstructure, chemical composition and temperature on the CCG and creep failure. In the first study the notch sensitivity of A508 material under constant ... A508 class 2 material with simulated coarse grained heat affected zone microstructure. Results Based on results of this work it cannot be precluded that no creep cracking will occur in nuclear pressure vessels...

  Innehållstyp: Dokument

• 2004:48 Feasibility Study of Coupling the CASMO-4/TABLES-3/SIMULATE-3 Code System to TRACE/PARCS

  01 januari 2004

  this, the Department of Reactor Physics at Chalmers has been asked to perform a feasibility study on possibility of coupling the code package CASMO/SIMULATE from Studsvik Scandpower to the TRACE/PARCS ... parameters. In the first part of the report, the TRACE/PARCS codes are presented and emphasis is put on the data required by the PARCS neutronic module. In the second part of the report, each of the codes...

  Innehållstyp: Dokument

• 2004:13 A Review of the Decommissioning Plan and Cost Estimate for the Studsvik Rock Facility (AM) for the Storage of Low and Intermediate Level Wastes (pdf 387 kB)

  01 januari 2004

  nuclear power utilities must under the so-called Studsvik Act (the complete translation is the Act on the Financing of the Management of Certain Radioactive Waste etc. (1988:1597)) contribute to the Swedish ... related facilities at the Studsvik site. The task to build up an appropriate capital fund will be based on the sum of individual cost estimates for the decontamination and decommissioning of relevant facilities...

  Innehållstyp: Dokument

• 2004:33 Assessment of Fuel Rod Failure Thresholds for Reactivity Initiated Accidents

  01 januari 2004

  than previously estimated. At the beginning of 1995 SKI issued fuel and cladding failure limits based on available test data. It was envisaged at that time that the failure limits should be re-evaluated when ... joined the OECD-IRSN CABRI water loop project at the end of 2000. The purpose was to gain information on the failure threshold for nuclear fuel cladding as a function of burnup, especially for modern cladding...

  Innehållstyp: Dokument

• 2004:54 Studies of Corrosion of Cladding Materials in Simulated BWR-environment Using Impedance Measurements

  01 januari 2004

  corrosion is one of the phenomena that limits the life time of nuclear fuel. Corrosion performance depends on the cladding material properties as well as operating conditions during the irradiation of the fuel ... an ideal situation, the oxide film formed on the surface of a material protects the material against further degradation. The degree of protection depends on the properties of the oxide. Since these properties...

  Innehållstyp: Dokument

• 2004:51 Investigation of the Potential for In-Vessel Melt Retention in the Lower Head of a BWR by Cooling through the Control Rod Guide Tubes

  01 januari 2004

  kW/m2; - for a day hot particulate debris bed: ~ 150 kW/m2; - for a melt pool with a crust formed on the CRGT surface: ~350 kW/m2. It is recommended that further investigations, both experimental and ... establish a water pool in the PWR cavity or BWR drywell, which should provide sufficient heat removal on the outside of the lower head to retain the melt within the vessel lower head. The Swedish BWRs...

  Innehållstyp: Dokument

• 2004:15 Omgivningskontrollprogram för de kärntekniska anläggningarna, revision

  omgivningskontroll för de fyra kärnkraftverken, anläggningarna i Studsvik samt Westinghouse Electric Sweden AB:s anläggningar i Västerås. Omgivningskontrollen ska ge en fortlöpande beskrivning av halten av olika radionuklider ... Ann-Marie Lindén SSM Svenska Rapporten innehåller ett reviderat program för omgivningskontroll för de fyra kärnkraftverken, anläggningarna i Studsvik samt Westinghouse Electric Sweden AB:s anläggningar i...

  Innehållstyp: Publikationer

• 2004:57 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods

  01 januari 2004

  Swedish Nuclear Power Inspectorate (SKI), contract No. 14.5-030917-200305001. The present report is based on work performed by Christophe Demazière, Carl Sunde, Johanna Wright and Imre Pázsit, with the latter ... large compared to the point- kinetic term of the neutron noise whose spatial structure does not depend on the position of the perturbation. The significance of the space-dependent global component is that...

  Innehållstyp: Dokument

• 2004:55 Development of an Input Model to MELCOR 1.8.5 for the Ringhals 3 PWR

  01 januari 2004

  Perspective Background Assessments of the source term for Swedish nuclear power reactors are based on calculations made by means of the severe accident analysis code MAAP. This code was developed for ... calculations of various postulated severe accident scenarios, although the first application is specifically on cases involving large hydrogen production. The input file is rather detailed with individual modelling...

  Innehållstyp: Dokument

• 2004:53 Studies of Corrosion of Cladding Materials in Simulated BWR-environment Using Impedance Measurements

  01 januari 2004

  corrosion is one of the phenomena that limits the life time of nuclear fuel. Corrosion performance depends on the cladding material properties well as operating conditions during the irradiation of the fuel. ... an ideal situation, the oxide film formed on the surface of a material protects the material against further degradation. The degree of protection depends on the properties of the oxide. Since these properties...

  Innehållstyp: Dokument