NS ICS 27.120.30

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Status: Check Published
Norwegian title: Samlingen inneholder alle norske standarder innenfor ICS 27.120.30: Fissile materialer
English title: The collection contains all norwegian standards within ICS 27.120.30: Fissile materials and nuclear fuel technology
Item type: Standardsamling
Language: Ukjent
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Innhold av samlingen (21)

NOK 630,00 (excl. VAT)

Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 2: Samples containing plutonium and uranium in the nanogram range and below (ISO 15366-2:2014)

LanguageEngelskEdition: 1 (2016-07-01)

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Re-sintering test for UO2, (U,Gd)O2 and (U,Pu)O2 pellets (ISO 15646:2014)

LanguageEngelskEdition: 1 (2016-07-01)

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NOK 630,00 (excl. VAT)

Nuclear fuel technology - Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range (ISO 15366-1:2014)

LanguageEngelskEdition: 1 (2016-07-01)

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NOK 530,00 (excl. VAT)

Nuclear energy - Determination of total hydrogen content in PuO2 and UO2 powders and UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method (ISO 15651:2015)

LanguageEngelskEdition: 1 (2018-01-01)

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NOK 530,00 (excl. VAT)

Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2 (ISO 21483:2013)

LanguageEngelskEdition: 1 (2018-01-01)

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NOK 775,00 (excl. VAT)

Guidance for gamma spectrometry measurement of radioactive waste (ISO 19017:2015)

LanguageEngelskEdition: 1 (2018-01-01)

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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 (ISO 16424:2012)

LanguageEngelskEdition: 1 (2018-01-01)

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Nuclear fuel technology — Dissolution of plutonium dioxide-containing materials — Part 2: Dissolution of MOX pellets and powders (ISO 18256-2:2019)

LanguageEngelskEdition: 2021-02 (2021-02-25)

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Nuclear fuel technology — Dissolution of plutonium dioxide-containing materials — Part 1: Dissolution of plutonium dioxide powders (ISO 18256-1:2019)

LanguageEngelskEdition: 2021-02 (2021-02-25)

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Nuclear fuel technology — Guidelines for ceramographic preparation of UO2 sintered pellets for microstructure examination (ISO 16793:2018)

LanguageEngelskEdition: 2021-02 (2021-02-25)

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NOK 775,00 (excl. VAT)

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 (ISO 8299:2019)

LanguageEngelskEdition: 2021-02 (2021-03-01)

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NOK 969,00 (excl. VAT)

Safe transport of radioactive materials — Leakage testing on packages (ISO 12807:2018)

LanguageEngelskEdition: 2021-02 (2021-03-01)

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Uranium dioxide powder — Determination of apparent density and tap density (ISO 9161:2019)

LanguageEngelskEdition: 2021-02 (2021-03-01)

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Nuclear energy — Nuclear fuel technology — Determination of plutonium in nitric acid solutions by spectrophotometry (ISO 9463:2019)

LanguageEngelskEdition: 2021-02 (2021-03-01)

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Nuclear energy — Fuel technology — Trunnion systems for packages used to transport radioactive material (ISO 10276:2019)

LanguageEngelskEdition: 2021-08 (2021-08-25)

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Nuclear fuel technology - Controlled-potential coulometric assay of plutonium (ISO 12183:2016)

LanguageEngelskEdition: 1 (2019-09-01)

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Nuclear energy - Determination of nitrogen content in UO2, (U,Gd)O2 and (U,Pu)O2 sintered pellets - Inert gas extraction and conductivity detection method (ISO 12799:2015)

LanguageEngelskEdition: 1 (2019-09-01)

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Nuclear fuel technology - Guidelines on the measurement of the specific surface area of uranium oxide powders by the BET method (ISO 12800:2017)

LanguageEngelskEdition: 1 (2019-09-01)

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Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method (ISO 21484:2017)

LanguageEngelskEdition: 1 (2019-09-01)

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Nuclear fuel technology - Sintered (U,Pu)O2 pellets - Guidance for ceramographic preparation for microstructure examination (ISO 22765:2016)

LanguageEngelskEdition: 1 (2019-09-01)

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Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes (ISO 18557:2017)

LanguageEngelskEdition: 2020-02 (2020-04-01)

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