Standards 16 through 19.9

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  1. HISTORICAL

    21056

    ANS 16.1-1986▹ [ Withdrawn ]

    This document has been replaced. View the most recent version.

    Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure

    standard by American Nuclear Society, 01/01/1986.

    Languages: English

    Historical Editions: ANS 16.1-2003 (R2017)

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  2. MOST RECENT

    1219385

    ANS 16.1-2003 (R2017)▹

    Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure

    standard by American Nuclear Society, 07/07/2003.

    Languages: English

    Historical Editions: ANS 16.1-1986

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  3. HISTORICAL

    21057

    ANS 18.1-1999▹ [ Withdrawn ]

    This document has been replaced. View the most recent version.

    Radioactive Source Term for Normal Operation of Light Water Reactors

    standard by American Nuclear Society, 01/01/1999.

    Languages: English

    Historical Editions: ANS 18.1-2016

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  4. MOST RECENT

    1936706

    ANS 18.1-2016▹

    Radioactive Source Term for Normal Operation of Light Water Reactors

    standard by American Nuclear Society, 11/01/2016.

    Languages: English

    Historical Editions: ANS 18.1-1999

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  5. HISTORICAL

    21058

    ANS 18.5-1982 (R1989)▹ [ Withdrawn ]

    This document has been replaced. View the most recent version.

    Surveys of Terrestrial Ecology Needed to License Thermal Power Plants

    standard by American Nuclear Society, 01/01/1982.

    Languages: English

    Historical Editions: ANS 2.25-1982 (R1989)

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  6. HISTORICAL

    21059

    ANS 19.1-1983 (R1989)▹ [ Withdrawn ]

    This document has been replaced. View the most recent version.

    Nuclear Data Sets for Reactor Design Calculations

    standard by American Nuclear Society, 01/01/1983.

    Languages: English

    Historical Editions: ANS 19.1-2002 (R2011)

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  7. MOST RECENT

    1219386

    ANS 19.1-2002 (R2011)▹

    Nuclear Data Sets for Reactor Design Calculations

    standard by American Nuclear Society, 07/23/2002.

    Languages: English

    Historical Editions: ANS 19.1-1983 (R1989)

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  8. MOST RECENT

    1848243

    ANS 19.10-2009 (R2016)▹

    Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals

    standard by American Nuclear Society, 02/24/2009.

    Languages: English

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  9. HISTORICAL

    740620

    ANS 19.11-1997 (W2017)▹ [ Withdrawn ]

    This document has been replaced. View the most recent version.

    Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors

    standard by American Nuclear Society, 09/25/1997.

    Languages: English

    Historical Editions: ANS 19.11-2017

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  10. MOST RECENT

    1952121

    ANS 19.11-2017▹

    Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors

    standard by American Nuclear Society, 04/11/2017.

    Languages: English

    Historical Editions: ANS 19.11-1997 (W2017)

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