ANS - American Nuclear Society: Recent submissions

Now showing items 81-87 of 87

    • ANS 57.8 

      Type: standard
      Source: ANS - American Nuclear Society:;2011
      Organization : ANS - American Nuclear Society
      Abstract: Scope and Purpose
      This standard describes requirements for the unique identification of fuel assemblies utilized in nuclear power plants. It defines the characters and proposed sequence to be used in ...

    • ANS 8.27 

      Type: standard
      Source: ANS - American Nuclear Society:;2008
      Organization : ANS - American Nuclear Society
      Abstract: This standard provides criteria for accounting for reactivity effects of fuel irradiation and radioactive decay in criticality safety control of storage, transportation, and disposal of commercial LWR UO2 fuel ...

    • ANS 10.7 

      Type: standard
      Source: ANS - American Nuclear Society:;2013
      Organization : ANS - American Nuclear Society
      Abstract: This standard provides minimum requirements for assurance that high-integrity software developed for use by the nuclear industry meets state-of-the-practice expectations for quality. The requirements in this standard are ...

    • ANS 58.11 

      Type: standard
      Source: ANS - American Nuclear Society:;2002
      Organization : ANS - American Nuclear Society
      Abstract: This standard provides design criteria for systems that perform the safety-related functions necessary to shut down a reactor and maintain it in a safe shutdown condition for selected design basis events; i.e., any design ...

    • ANS 6.4 

      Type: standard
      Source: ANS - American Nuclear Society:;2006
      Organization : ANS - American Nuclear Society
      Abstract: This standard contains methods and data needed to calculate the concrete thickness required for radiation shielding in nuclear power plants. Where possible, specific recommendations are made regarding radiation attenuation ...

    • ANS 58.14 

      Type: standard
      Source: ANS - American Nuclear Society:;2011
      Organization : ANS - American Nuclear Society
      Abstract: This standard specifies criteria for the safety classification of items (SSCs and parts, including consumables) in a LWR nuclear power plant as safety-related (Q), non-safety-related with augmented requirements (A), or ...

    • ANS 15.8 

      Type: standard
      Source: ANS - American Nuclear Society:;2013
      Organization : ANS - American Nuclear Society
      Abstract: This standard provides criteria for quality assurance in the design, construction, operation, and decommissioning of research reactors.