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Din avgränsning ger 77 träffar.

• 2005:16 Radon Risk Map of Estonia; Explanatory text to the Radon Risk Map Set of Estonia at the scale of 1:500,000

  01 augusti 2005

  is used in a building. The following activity concentration index (I) is derived for identifying whether a dose criterion is met: I = CRa/ 300 + CTh/200 + CK/3000 where CRa, CTh, CK are the radium, thorium ... mSva-1 Materials used in bulk amounts, e.g. concrete I ≤ 0.5 I ≤1 Superficial and other materials with restricted use: tiles, boards, etc I ≤ 2 I ≤ 6 16 3.2. Estonian regulations and guidelines...

  Innehållstyp: Dokument

• 2005:64 Investigating conceptual models for physical property couplings in solid solution models of cement

  01 januari 2005

  1626 kB ... Transition State Theory rate equation (e.g. Helgeson et al., 1984) of the form, ⎟⎟⎠ ⎞ ⎜⎜⎝ ⎛ −= 1 i i ii i K QAk dt dC . Here ik (mol m -2 y-1) is the rate of the reaction per surface area of end member ... occupied by the minerals is therefore ∑ iiMvNθ m3, where Mvi denotes the molar volume of mineral i (m3/mol). Thus 1MvN ii =+ ∑θθ , and so † Taken...

  Innehållstyp: Dokument

• 2005:58 The Swedish Concept for Disposal of Spent Nuclear Fuel: Differences Between Vertical and Horizontal Waste Canister Emplacement (1,08 MB)

  01 januari 2005

  1106 kB ... the author/authors and do not necessarily coincide with those of the SKI. i Executive Summary The Swedish Nuclear Power Inspectorate (SKI) is preparing for the review of licence ... and used for transporting the waste to the deposition drift. Little information is provided on (i) the procedure or method to be used for supercontainer 6 assembly, and (ii) the temperature...

  Innehållstyp: Dokument

• 2005:34 An Applied Study on the Decontamination and Decommissioning of the Map Tube Facility 317 Area Argonne National Laboratory, Chicago (pdf 2,24MB)

  01 januari 2005

  and Dismantling Implementation................................................... 3-1 3.2.1 Phase I - Map Tube Facility Characterization............................................. 3-1 3.2.2 Phase II ... characterization was conducted. For Area 317, the characterization process was reported in, “ANL Area 317 Phase I & II Characterization Report” (ANL-TR-0001). The process of evaluating SWMUs within the 317/319/ENE...

  Innehållstyp: Dokument

• 2005:65 Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co’s RD&D Programme 2004

  01 januari 2005

  1847 kB ... December 2005 ISSN 1104–1374 ISRN SKI-R-05/31-SE www.ski.se S TA T E N S K Ä R N K R A F T I N S P E K T I O N Swedish Nuclear Power Inspectorate POST/POSTAL ADDRESS SE-106 58 Stockholm BESÖK/OFFICE ... Co’s RD&D Programme 2004 Review Report SKI’s Evaluation of the Swedish Nuclear Fuel and i Contents Summary ..............................................................................

  Innehållstyp: Dokument

• 2005:32e Safety and Radiation Protection at Swedish Nuclear Power Plants 2004

  01 maj 2005

  interest for a wider readership. The ageing of electrical cables and other equipment in the facilities’ I&C systems has been observed by SKI. Supervisory work has so far shown that these issues are largely ... leaktightness and integrity in time. The ageing of electrical cables and other equipment in the I&C systems has attracted international attention. Observed and possible problems were identified and...

  Innehållstyp: Dokument

• 2005:15 Human Factors Engineering Plan for Reviewing Nuclear Plant Modernization Programs

  01 januari 2005

  HFE human factors engineering HRA human reliability analysis HSI human-system interface I&C instrumentation and control IAEA International Atomic Energy Agency IEC International Electrotechnical ... version of the review plan was then used to review of the major instrumentation 2 and control (I&C) system and control room modernization program at Unit 1 of the Oskarshamn Nuclear Power Station...

  Innehållstyp: Dokument

• 2005:24 DECOVALEX III/BENCHPAR PROJECTS Implications of Thermal-Hydro-Mechanical Coupling on the Near-Field Safety of a Nuclear Waste Repository

  01 januari 2005

  laboratory experiments. DECOVALEX II, started in 1996, built on the experience gained in DECOVALEX I by modeling larger tests conducted in the field. DECOVALEX III, started in 1999 following the completion ... obtained, as compared with the Task 2C results of DECOVAEX II. The measures taken for improvement were: i) Parameter changes (reduced rock mass permeability and rock mass thermal expansion by the SKI/KTH team...

  Innehållstyp: Dokument

• 2005:19 DECOVALEX III PROJECT Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories

  01 januari 2005

  laboratory experiments. DECOVALEX II, started in 1996, built on the experience gained in DECOVALEX I by modeling larger tests conducted in the field. DECOVALEX III, started in 1999 following the completion ... nuclear fuel waste repositories. During the first stage (May 1992 to March 1995), called DECOVALEX I, the main objective was to develop computer codes for coupled T-H-M processes and their verification...

  Innehållstyp: Dokument

• 2005:38 A Model Study of Costs Estimates of Decontamination and Decommissioning with an Emphasis to Derive Cost Functions for Alpha-Contaminated Material Using OMEGA Code (582 kB)

  01 januari 2005

  systems and building objects was also achieved. In 1994 the Project for the NPP A-1 decommissioning I. stage was developed and approved. The purpose of the project is to achieve the radiological status ... (non-accident) NPPs at final shutdown by the end of 2007. Important milestones within the frame of the I. stage of decommissioning were achieved by the year 2000, when all spent fuel was successfully transported...

  Innehållstyp: Dokument