
Items to be displayed:
| Standard and/or project | Stage | ICS |
|---|---|---|
| ISO 1709:1995 Nuclear energy -- Fissile materials -- Principles of criticality safety in storing, handling and processing | 90.93 | 27.120.30 |
| ISO 2855:1976 Radioactive materials -- Packagings -- Test for contents leakage and radiation leakage | 90.60 | 13.280 |
| ISO 6962:2004 Nuclear energy -- Standard method for testing the long-term alpha irradiation stability of matrices for solidification of high-level radioactive waste | 90.60 | 13.030.30 13.280 |
| ISO 7097-1:2004 Nuclear fuel technology -- Determination of uranium in solutions, uranium hexafluoride and solids -- Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method | 90.60 | 27.120.30 |
| ISO 7097-2:2004 Nuclear fuel technology -- Determination of uranium in solutions, uranium hexafluoride and solids -- Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method | 90.60 | 27.120.30 |
| ISO 7195:2005 Nuclear energy -- Packaging of uranium hexafluoride (UF6) for transport | 90.92 | 27.120.30 |
| ISO 7476:2003 Nuclear fuel technology -- Determination of uranium in uranyl nitrate solutions of nuclear grade quality -- Gravimetric method | 90.93 | 27.120.30 |
| ISO 7753:1987 Nuclear energy -- Performance and testing requirements for criticality detection and alarm systems | 90.93 | 27.120.10 |
| ISO 8298:2000 Nuclear fuel technology -- Determination of milligram amounts of plutonium in nitric acid solutions -- Potentiometric titration with potassium dichromate after oxidation by Ce(IV) and reduction by Fe(II) | 90.93 | 27.120.30 |
| ISO 8299:2005 Nuclear fuel technology -- Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry | 90.20 | 27.120.30 |
| ISO 8300:1987 Determination of plutonium content in plutonium dioxide (PuO2) of nuclear grade quality -- Gravimetric method | 90.92 | 27.120.30 |
| ISO 8425:1987 Determination of plutonium in pure plutonium nitrate solutions -- Gravimetric method | 90.92 | 27.120.30 |
| ISO 9005:2007 Nuclear energy -- Uranium dioxide powder and sintered pellets -- Determination of oxygen/uranium atomic ratio by the amperometric method | 90.93 | 27.120.30 |
| ISO 9006:1994 Uranium metal and uranium dioxide powder and pellets -- Determination of nitrogen content -- Method using ammonia-sensing electrode | 90.93 | 27.120.30 |
| ISO 9161:2004 Uranium dioxide powder -- Determination of apparent density and tap density | 90.60 | 27.120.30 |
| ISO 9278:2008 Nuclear energy - Uranium dioxide pellets -- Determination of density and volume fraction of open and closed porosity | 90.60 | 27.120.30 |
| ISO 9279:1992 Uranium dioxide pellets -- Determination of density and total porosity -- Mercury displacement method | 90.93 | 27.120.30 |
| ISO 9463:2009 Nuclear energy -- Nuclear fuel technology -- Determination of plutonium in nitric acid solutions by spectrophotometry | 60.60 | 27.120.30 |
| ISO 9889:1994 Determination of carbon content in uranium dioxide powder and sintered pellets -- Resistance furnace combustion -- Titrimetric/coulometric/infrared absorbtion method | 90.93 | 27.120.30 |
| ISO 9891:1994 Determination of carbon content in uranium dioxide powder and sintered pellets -- High-frequency induction furnace combustion -- Titrimetric/coulometric/infrared absorption methods | 90.93 | 27.120.30 |
| ISO 9892:1992 Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions -- Determination of fluorine content -- Fluoride ion selective electrode method | 90.93 | 27.120.30 |
| ISO 9894:1996 Subsampling of uranium hexafluoride in the liquid phase | 90.93 | 27.120.30 |
| ISO 10276:2010 Nuclear energy -- Fuel technology -- Trunnions for packages used to transport radioactive material | 60.60 | 27.120.30 |
| ISO 10980:1995 Validation of the strength of reference solutions used for measuring concentrations | 90.93 | 27.120.30 |
| ISO 10981:2004 Nuclear fuel technology -- Determination of uranium in reprocessing-plant dissolver solution -- Liquid chromatography method | 90.60 | 27.120.30 |
| ISO 11311:2011 Nuclear criticality safety -- Critical values for homogeneous plutonium-uranium oxide fuel mixtures outside of reactors | 60.60 | 27.120.30 |
| ISO 11320:2011 Nuclear criticality safety -- Emergency preparedness and response | 60.60 | 27.120.30 |
| ISO 11482:1993 Guidelines for plutonium dioxide (PuO2) sampling in a nuclear reprocessing plant | 90.60 | 27.120.30 |
| ISO 11483:2005 Nuclear fuel technology -- Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry | 90.20 | 27.120.30 |
| ISO 11599:1997 Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste | 90.60 | 27.120.20 13.030.40 |
| ISO 11932:1996 Activity measurements of solid materials considered for recycling, re-use or disposal as non-radioactive waste | 90.60 | 13.280 13.030.10 |
| ISO 12183:2005 Nuclear fuel technology -- Controlled-potential coulometric assay of plutonium | 90.20 | 27.120.30 |
| ISO 12184:1994 Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U,Pu)O2 | 90.93 | 27.120.30 |
| ISO 12795:2004 Nuclear fuel technology -- Uranium dioxide powder and pellets -- Determination of uranium and oxygen/uranium ratio by gravimetric method with impurity correction | 90.60 | 27.120.30 |
| ISO 12800:2003 Nuclear fuel technology -- Guide to the measurement of the specific surface area of uranium oxide powders by the BET method | 90.93 | 27.120.30 |
| ISO 12803:1997 Representative sampling of plutonium nitrate solutions for determination of plutonium concentration | 90.60 | 27.120.30 |
| ISO 12807:1996 Safe transport of radioactive materials -- Leakage testing on packages | 90.93 | 13.280 27.120.30 |
| ISO 13463:1999 Nuclear-grade plutonium dioxide powder for fabrication of light water reactor MOX fuel -- Guidelines to help in the definition of a product specification | 90.93 | 27.120.30 |
| ISO 13464:1998 Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants -- Combined method using K-absorption edge and X-ray fluorescence spectrometry | 90.93 | 27.120.30 |
| ISO 13465:2009 Nuclear energy -- Nuclear fuel technology -- Determination of neptunium in nitric acid solutions by spectrophotometry | 60.60 | 27.120.30 |
| ISO 14850-1:2004 Nuclear energy -- Waste-packages activity measurement -- Part 1: High-resolution gamma spectrometry in integral mode with open geometry | 90.60 | 17.240 13.030.30 |
| ISO 14943:2004 Nuclear fuel technology -- Administrative criteria related to nuclear criticality safety | 90.60 | 27.120.20 |
| ISO 15366:1999 Nuclear energy -- Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and dilution analysis by solvent chromatography | 90.92 | 27.120.30 |
| ISO 15647:2004 Nuclear energy -- Isotopic analysis of uranium hexafluoride -- Double-standard gas-source mass spectrometric method | 90.60 | 27.120.30 |
| ISO 16424:2012 Nuclear energy -- Evaluation of homogeneity of Gd distribution within gadolinium fuel blends and determination of Gd2O3 content in gadolinium fuel pellets by measurements of uranium and gadolinium elements | 60.60 | 27.120.30 |
| ISO 16793:2005 Nuclear fuel technology -- Guide for ceramographic preparation of UO2 sintered pellets for microstructure examination | 90.20 | 27.120.30 |
| ISO 16794:2003 Nuclear energy -- Determination of carbon compounds and fluorides in uranium hexafluoride infrared spectrometry | 90.20 | 27.120.30 |
| ISO 16795:2004 Nuclear energy -- Determination of Gd2O3 content of gadolinium fuel pellets by X-ray fluorescence spectrometry | 90.60 | 27.120.30 |
| ISO 16796:2004 Nuclear energy -- Determination of Gd2O3 content in gadolinium fuel blends and gadolinium fuel pellets by atomic emission spectrometry using an inductively coupled plasma source (ICP-AES) | 90.60 | 27.120.30 |
| ISO 16797:2004 Nuclear energy -- Soxhlet-mode chemical durability test -- Application to vitrified matrixes for high-level radioactive waste | 90.60 | 27.120.99 13.030.30 |
| ISO 18213-1:2007 Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 1: Procedural overview | 90.93 | 27.120.30 |
| ISO 18213-2:2007 Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 2: Data standardization for tank calibration | 90.93 | 27.120.30 |
| ISO 18213-3:2009 Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 3: Statistical methods | 60.60 | 27.120.30 |
| ISO 18213-4:2008 Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 4: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, slow bubbling rate | 90.60 | 27.120.30 |
| ISO 18213-5:2008 Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 5: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, fast bubbling rate | 90.60 | 27.120.30 |
| ISO 18213-6:2008 Nuclear fuel technology -- Tank calibration and volume determination for nuclear materials accountancy -- Part 6: Accurate in-tank determination of liquid density in accountancy tanks equipped with dip tubes | 90.60 | 27.120.30 |
| ISO 21238:2007 Nuclear energy -- Nuclear fuel technology -- Scaling factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants | 90.93 | 27.120.30 |
| ISO 21484:2008 Nuclear fuel technology -- Determination of the O/M ratio in MOX pellets -- Gravimetric method | 90.92 | 27.120.30 17.240 |
| ISO 21614:2008 Determination of carbon content of UO2, (U, Gd)O2 and (U, Pu)O2 powders and sintered pellets -- Combustion in a high-frequency induction furnace -- Infrared absorption spectrometry | 90.60 | 27.120.20 |
| ISO 21847-1:2007 Nuclear fuel technology -- Alpha spectrometry -- Part 1: Determination of neptunium in uranium and its compounds | 90.93 | 27.120.30 |
| ISO 21847-2:2007 Nuclear fuel technology -- Alpha spectrometry -- Part 2: Determination of plutonium in uranium and its compounds | 90.93 | 27.120.30 |
| ISO 21847-3:2007 Nuclear fuel technology -- Alpha spectrometry -- Part 3: Determination of uranium 232 in uranium and its compounds | 90.93 | 27.120.30 |
| ISO 22875:2008 Nuclear energy -- Determination of chlorine and fluorine in uranium dioxide powder and sintered pellets | 90.60 | 27.120.30 |
| ISO 26062:2010 Nuclear technology -- Nuclear fuels -- Procedures for the measurement of elemental impurities in uranium- and plutonium-based materials by inductively coupled plasma mass spectrometry | 60.60 | 27.120.30 |
| ISO 27467:2009 Nuclear criticality safety -- Analysis of a postulated criticality accident | 60.60 | 27.120.30 |
| ISO 27468:2011 Nuclear criticality safety -- Evaluation of systems containing PWR UOX fuels -- Bounding burnup credit approach | 60.60 | 27.120.30 |