• 0
    • ارسال درخواست
    • حذف همه
    • Industrial Standards
    • Defence Standards
  • درباره ما
  • درخواست موردی
  • فهرست استانداردها
    • Industrial Standards
    • Defence Standards
  • راهنما
  • Login
  • لیست خرید شما 0
    • ارسال درخواست
    • حذف همه
Search 
  •   YSE
  • Industrial Standards
  • ANS - American Nuclear Society
  • Search
  •   YSE
  • Industrial Standards
  • ANS - American Nuclear Society
  • Search
  • All Fields
  • Title(or Doc Num)
  • Organization
  • Year
  • Subject
Advanced Search
JavaScript is disabled for your browser. Some features of this site may not work without it.

Archive

Organization

Year

Type

Language (ISO)

Content Type

Search

Show Advanced FiltersHide Advanced Filters

Filters

Use filters to refine the search results.

Now showing items 81-87 of 87

    • Relevance
    • Title Asc
    • Title Desc
    • Year Asc
    • Year Desc
    • 5
    • 10
    • 20
    • 40
    • 60
    • 80
    • 100
  • Export
    • CSV
    • RIS
    • Sort Options:
    • Relevance
    • Title Asc
    • Title Desc
    • Issue Date Asc
    • Issue Date Desc
    • Results Per Page:
    • 5
    • 10
    • 20
    • 40
    • 60
    • 80
    • 100

    ANS 2.15: criteria for modeling and calculating atmospheric dispersion of routine radiological releases from nuclear facilities 

    Type: standard
    Source: ANS - American Nuclear Society:;2013
    Organization : ANS - American Nuclear Society
    Abstract: Introduction and scope
    In the decades prior to this standard, significant enhancements have been made in the area of atmospheric dispersion modeling. Considerable advances have occurred in our understanding ...
    Request PDF

    ANS 8.1: Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors 

    Type: standard
    Source: ANS - American Nuclear Society:;2007
    Organization : ANS - American Nuclear Society
    Abstract: This standard is applicable to operations with fissionable materials outside nuclear reactors, except for the assembly of these materials under controlled conditions, such as in critical experiments. Generalized basic ...
    Request PDF

    ANS 19.11: English -- Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Pressurized Water Reactors 

    Type: standard
    Source: ANS - American Nuclear Society:;2017
    Organization : ANS - American Nuclear Society
    Abstract: Scope: This standard 1) provides guidance and specifies criteria for determining the MTC in PWRs. Measurement of the isothermal temperature coefficient of reactivity (ITC) at hot-zero-power (HZP) conditions is covered in ...
    Request PDF

    ANS 8.1 ERTA: Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors - Errata to 1998 R2007 

    Type: standard
    Source: ANS - American Nuclear Society:;
    Organization : ANS - American Nuclear Society
    Request PDF

    ANS 2.17: evaluation of subsurface radionuclide transport at commercial nuclear power plants 

    Type: standard
    Source: ANS - American Nuclear Society:;2010
    Organization : ANS - American Nuclear Society
    Abstract: This national standard establishes the requirements for evaluating the occurrence and movement of radionuclides in the subsurface resulting from abnormal radionuclide releases at commercial nuclear power plants.
    This ...
    Request PDF

    ANS 58.14: Safety and Pressure Integrity Classification Criteria for Light Water Reactors 

    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 ...
    Request PDF

    ANS 15.8: Quality assurance program requirements for research reactors 

    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.
    Request PDF
    • 1
    • . . .
    • 6
    • 7
    • 8
    • 9
    DSpace software copyright © 2017-2020  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian
     
    DSpace software copyright © 2017-2020  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
    yabeshDSpacePersian