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Standards in the ASU Library: AGA-ANS: ANS

List of available industry standards from organizations whose acronyms are between "AGA" and "ANS".

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    AA-AFPA

    AGA-ANS

    ANSI

    ANSLG-ARMA

    AS-AWWA

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Please note ...

The ASU Library's standards collection is intended for the use of ASU faculty, staff and currently enrolled students. 

Individuals not affliated with ASU who live in the Phoenix metropolitan area are welcome to come to the Noble Science and Engineering Library on the Tempe campus to view the standards.  Items in the collection are not available for checkout or loan to other libraries; because of copyright restrictions, we do not provide photocopies or scanned copies to those unaffiliated with ASU.  

ANS (American Nuclear Society)

The following ANS standards are available in paper copy in the Noble Science & Engineering Library on the Tempe Campus, unless noted otherwise. Standards housed in Noble are "Library use only" and are not available for checkout.

  • ANS 1 2007(rev of 2000),1975,1972 (Conduct of Critical Experiments)
  • ANS 2.2 1988,1978 (Earthquake Instrumentation Criteria for Nuclear Power Plants)
  • ANS 2.3
  • 1983 (Immediate Evacuation Signal for Use in Industrial Installation)
  • 1979 (Estimating Tornado and Extreme Wind Characteristics at Nuclear Power Sites)
  • ANS 2.5 1984 (Determining Meteorological Information at Nuclear Power Sites)
  • ANS 2.7 1982 (Criteria and Guidelines for Assessing Capability for Surface Faulting at Nuclear Power Plant Sites)
  • ANS 2.8 1992,1981,1976 (Determining Design Basis Flooding at Power Reactor Sites)
  • ANS 2.9 1980 (Evaluation of Ground Water Supply for Nuclear Power Sites)
  • ANS 2.10 1979 (Guidelines for Retrieval, Review, Processing and Evaluation of records obtained from Seismic Instrumentation)
  • ANS 2.11 1978 (Guidelines for Evaluating Site-Related Geotechnical Parameters at Nuclear Power Sites)
  • ANS 2.12 1978 (Guidelines fo Combining Natural and External Man-Made Hazards at Power Reactor Sites)
  • ANS 2.13 1979 (Evaluation of Surface-Water Supplies for Nuclear Power Sites)
  • ANS 2.17 1980 (Evaluation of Radionuclide Transport in Ground Water for Nuclear Power Sites)
  • ANS 2.19 1981 (Guidelines for Establishing Site-Related Parameters for Site Selection and Design of an Independent Spent Fuel Storage Installation (Water pool type))
  • ANS 2.27 2008 (criteria for investigations of nuclear facility sites for seismic hazard assessments)
  • ANS 2.29 2008 (probabilistic seismic hazards analysis)
  • ANS 3 1971 (Recommended Programming Practices to Facilitate the Interchange of Digital Computer Programs)
  • ANS 3.1 1993,1987,1981,1978 (Selection, Qualification, and Training of Personnel for Nuclear Power Plants)
  • ANS 3.2  2006,1988,1982,1976 (Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants)
  • ANS 3.3 1988,1982 (Security for Nuclear Power Plants)
  • ANS 3.4 1983,1976 (Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants)
  • ANS 3.5 1998,1993,1985,1981,1979 (Nuclear Power Plant Simulators for use in Operator Training and Examination)
  • ANS 3.7.1 1979 (Facilities and Medical Care for on-site Nuclear Power Plant Radiological Emergencies)
  • ANS 3.7.2 1979 (Emergency Control Centers for Nuclear Power Plants)
  • ANS 3.7.3 1979 (Radiological Emergency Preparedness Exercises for Nuclear Power Plants)
  • ANS 3.8.1 1987 (Criteria for Emergency Response Functions and Organizations)
  • ANS 3.8.2 1987 (Criteria for Functional and Physical Characteristics of Emergency Response Facilities)
  • ANS 3.8.3 1987 (Criteria for Emergency Response Plans and Implementing Procedures)
  • ANS 3.8.5 1992 (Criteria for Emergency Radiological Field Monitoring, Sampling, and Analysis)
  • ANS 3.8.7 1998 (Criteria for Planning, Developing, Conduct, and Evaluation of drills and Exercises for Emergency Preparedness)
  • ANS 3.11 2005,2000 (Determining Meteorological Information at Nuclear Facilities)
  • ANS 4.1 1978 (Design Basis Criteria for Safety Systems in Nuclear Power Generating Stations)
  • ANS 4.5 1980 (Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors)
  • ANS 5.1 1979,1971 (Decay Heat Power in Light Water Reactors)
  • ANS 5.4 1982 (Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel)
  • ANS 5.10 1998 (Airborne Release Fractions at Non-Reactor Nuclear Facilities)
  • ANS 6.1.1 1991,1977 (Neutron and Gamma-Ray fluence-to-dose Factors)
  • ANS 6.1.2 1999,1989,1983 (Neutron and Gamma-ray cross sections for nuclear radiation protection calculations for nuclear power plants)
  • ANS 6.3.1 1980, 1987 w/ reaf 2007 (Program for Testing Radiation Shields in Light ...)
  • ANS 6.4  2006,1985,1977 (Nuclear analysis and design of concrete radiation shielding for nuclear power plants)
  • ANS 6.4.2 2006,1985 (Specification for Radiation Shielding Materials)
  • ANS 6.4.3 1991 (Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials)
  • ANS 6.5 (Also Labeled as ANS 19.2 and ANS 50) (Trial Use Nuclear Glossary)
  • ANS 6.6.1 (R 1998),1987,1979 (Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plants)
  • ANS 6.8.1 1981 (Location and Design Criteria for Area Radiation Monitoring Systems for Light Water Nuclear Reactors)
  • ANS 8.1 1998,1983,1975 (Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors)
  • ANS 8.3 1986,1979 (Criticality Accident Alarm System)
  • ANS 8.5 1986,1979 (Use of borosilicate-glass raschig rings as a neutron absorber in solutions of fissile material)
  • ANS 8.6 1983,1975 (Safety in conducting subcritical neutron-multiplication measurements in situ)
  • ANS 8.7 2007(rev),1998,1975 (Nuclear Criticality Safety in the Storage of Fissile Materials)
  • ANS 8.9 1987,1978 (Nuclear criticality safety criteria for steel-pipe intersections containing aqueous solutions of fissile material)
  • ANS 8.10 1983,1975 (Criteria for nuclear criticality safety controls in operations with shielding and confinement)
  • ANS 8.11 1975 (Validation of calculational methods for nuclear criticality safety)
  • ANS 8.12 1987,1978 (Nuclear criticality control and safety of plutonium-uranium fuel mixtures outside reactors)
  • ANS 8.15 1981 (Nuclear criticality control of special actinide elements)
  • ANS 8.17 1984 (Criticality safety criteria for the handling, storage, and transportation of LWR fuel outside reactors)
  • ANS 8.19 2005, 1984 (Administrative practices for nuclear criticality safety)
  • ANS 8.20 1991 (Nuclear criticality safety training)
  • ANS 8.23 2007 (Nuclear criticality accident emergency planning and response)
  • ANS 8.24 2007 (Validation of neutron transport methods for nuclear criticality safety calculations)
  • ANS 8.26 2007 (Criticality Safety Engineer Training and Qualification program)
  • ANS 8.27 2008 (burnup credit for LWR fuel)
  • ANS 10.2 2000,1982
  • ANS 10.3 1995,1986,1973
  • ANS 10.4 2008,1987 (Verification and Validation of Non-Safety-Related Scientific and Engineering Computer Programs for the Nuclear Industry)
  • ANS 10.5 1994,1986,1979
  • ANS 14.1 1975
  • ANS 15.1 2007, 1990,1982 (Development of technical specifications for research reactors)
  • ANS 15.2 1999,1990,1974
  • ANS 15.3 1974
  • ANS 15.4 2007,1988,1977 (Selection and Training of Personnel for Research Reactors)
  • ANS 15.6 1974
  • ANS 15.7 1977
  • ANS 15.8 1976
  • ANS 15.10 1994,1981
  • ANS 15.11 1993,1987,1977
  • ANS 15.12 1977
  • ANS 15.15 1978
  • ANS 15.16 2008, 1982,1978 (emergency planning for research reactors)
  • ANS 15.17 1981
  • ANS 15.18 1979
  • ANS 15.19 1991
  • ANS 16.1 2003, 1986 (measurement of the leachability of solidified low-level radioactive wastes by a short-term test procedure)
  • ANS 18.1 1999,1976
  • ANS 18.5 1982
  • ANS 19.1 1983,1975
  • ANS 19.2 (See ANS 6.5)
  • ANS 19.3 2005,1983,1975
  • ANS 19.3.4 2002, 1976 (the determination of thermal energy deposition rates in nuclear reactors)
  • ANS 19.4 1976
  • ANS 19.5 1978
  • ANS 19.6.1 2005, 1997,1985
  • ANS 19.11 1997
  • ANS 40.35 1991,1984
  • ANS 40.37 1993
  • ANS 50 (See ANS 6.5)
  • ANS 51.1 1983
  • ANS 51.4 1977
  • ANS 51.7 1976
  • ANS 51.8 1975
  • ANS 51.10 1991, 1979 (Auxiliary Feedwater System for Pressurized Water Reactors)
  • ANS 52.1 1983,1978
  • ANS 54.1 1989,1975
  • ANS 54.2 1985
  • ANS 54.6 1979
  • ANS 54.8 1988
  • ANS 55.1 1992,1979
  • ANS 55.2 1976
  • ANS 55.3 1976
  • ANS 55.4 1993,1979
  • ANS 55.6 1979
  • ANS 56.2 1984,1976
  • ANS 56.3 1977
  • ANS 56.4 1983
  • ANS 56.5 1979
  • ANS 56.6 1986,1978
  • ANS 56.7 1978
  • ANS 56.8 1987,1981
  • ANS 56.10 1982
  • ANS 56.11 1988
  • ANS 57.1 1992,1980
  • ANS 57.2 1983,1976
  • ANS 57.3 1983
  • ANS 57.5 1981,1978
  • ANS 57.7 1988,1981
  • ANS 57.8 1978
  • ANS 57.9 1992,1984
  • ANS 57.10 1987
  • ANS 58.2 1980
  • ANS 58.3 1992, 1977
  • ANS 58.4 1979
  • ANS 58.6 1983
  • ANS 58.8 1994, 1984 (time response design criteria for safety-related operator actions)
  • ANS 58.9 1981
  • ANS 58.11 1983
  • ANS 58.21 2007
  • ANS 58.23 2007 (Fire PRA Methodology)
  • ANS 59.1 1986,1979
  • ANS 59.2 1985
  • ANS 59.3 1992,1984,1977
  • ANS 59.4 1979
  • ANS 59.51 1976
  • ANS E 1.1 1999
  • ANS X 9.20 1998
  • ANS X 9.24 1998
  • ANS X 9.29 1998
  • ANS X 9.49 1998
  • ANS X 9.62 1998
  • ANS X 9.69 1998
  • ANS N 18.8 1973
  • ANS N 18.10 1973
  • ANS N 18-20 1976
  • ANS N 212 1974
  • ANS N 661 1975

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