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ANS: American Nuclear Society

ANS, the American Nuclear Society, is a nonprofit, international, scientific, and educational organization. It was established by a group of individuals who recognized the need to unify professional activities within the various fields of nuclear science and technology. Standards from ANS are available both individually, directly through the ANSI webstore, and as part of a Standards Subscription. If you or your organization are interested in easy, managed, online access to standards that can be shared, a Standards Subscription may be what you need - please contact us at: StandardsSubscriptions@ansi.org or 1-212-642-4980 or Request Proposal Price.

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ANSI/ANS-2.26-2004 (R2017)

Categorization of Nuclear Facility Structures, Systems, and Components for Seismic Design

This standard provides: (i) criteria for selecting the Seismic Design Category (SDC) for nuclear facility structures, systems, and components (SSCs) to achieve earthquake safety and (ii) criteria and guidelines for selecting Limit States for these SSCs to govern their seismic design. The Limit States are selected to ensure the desired safety performance in an earthquake. The Seismic Design Categories (SDCs) used in this standard are not the same as the SDCs referred to in the International Building Code (IBC).


ANSI/ANS-3.2-2012 (R2017)

Managerial, Administrative, and Quality Assurance Controls for the Operational Phase of Nuclear Power Plants

This standard provides requirements and recommendations for managerial and administrative controls to ensure that activities associated with operating a nuclear power plant are carried out without undue risk to the health and safety of the public. This standard provides requirements for implementing managerial and administrative controls consistent with requirements of 10 CFR 50, Appendix B.


ANSI/ANS-15.8-1995 (R2013)

Quality Assurance Program Requirements for Research Reactors

This standard provides criteria for quality assurance in the design, construction, operation, and decommissioning of research reactors.


ANSI/ANS-15.8-1995 (R2013)

Quality Assurance Program Requirements for Research Reactors

This standard provides criteria for quality assurance in the design, construction, operation, and decommissioning of research reactors.


ANSI/ANS-3.1-2014 (R2020)

Selection, Qualification, and Training of Personnel for Nuclear Power Plants

This standard provides criteria for the selection, qualification, and training of personnel for nuclear power plants. The qualifications of personnel in the operating organizations appropriate to safe and efficient operation of a nuclear power plant are addressed in terms of the minimum education, experience, and training requirements. Requirements of this standard do not apply to test, mobile, training and research reactors.


ANSI/ANS-15.16-2015

Emergency Planning for Research Reactors

This standard identifies the elements of an emergency plan that describes the approach to coping with emergencies and minimizing the consequences of accidents at research reactor facilities. The emphasis given each of these elements shall be commensurate with the potential risk involved.


ANSI/ANS-8.1-2014

Nuclear Criticality Safety in Operations with Fissionable Material Outside Reactors

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 criteria are presented and limits are specified for some single fissionable units of simple shape containing 233U, 235U, or 239Pu, but not for multiunit arrays. Subcritical limits for certain multiunit arrays are contained in American National Standard Nuclear Criticality Safety in the Storage of Fissile Materials, ANSI/ANS-8.7-1998 (R2012). Requirements are stated for validation of any calculational method used in assessing nuclear criticality safety. This standard does not include the details of administrative controls, the design of processes or equipment, the description of instrumentation for process control, nor detailed criteria to be met in transporting fissionable materials. Guidance for transporting LWR fuel is contained in American National Standard Criticality Safety Criteria for the Handling, Storage, and Transportation of LWR Fuel Outside Reactors, ANSI/ANS-8.17-2004 (R2009).


ANSI/ANS-10.4-2008 (R2016)

Verification and Validation of Non-Safety-Related Scientific and Engineering Computer Programs for the Nuclear Industry

This standard provides guidelines for the verification and validation (V&V) of non-safety-related scientific and engineering computer programs developed for use by the nuclear industry. The scope is restricted to research and other non-safety-related, noncritical applications.


ANSI/ANS-5.1-2014 (R2019)

Decay Heat Power in Light Water Reactors

This standard sets forth values for the decay heat power from fission products and actinides following shutdown of light water reactors (LWRs) using nuclear fuel initially containing 235U and 238U. The decay heat power from fission products is presented in tables and equivalent analytical representations. Contributions from the decay of 239U and 239Np, and the contributions from all other actinides, are represented separately. Methods are described that account for the reactor operating history, for the effect of neutron capture in fission products, and for assessing the uncertainty in the resultant decay heat power. The standard applies to decay times up to 1010 s after shutdown.


ANSI/ANS-2.3-2011 (R2016)

Estimating Tornado, Hurricane, and Extreme Straight Line Wind Characteristics at Nuclear Facility Sites

This standard establishes guidelines to estimate the frequency of occurrence and the magnitude of parameters associated with rare meteorological events such as tornadoes, hurricanes, and extreme straight line winds at nuclear facility sites within the continental United States. The parameters addressed include the following: maximum wind speed ~e.g., translational, rotational, and total!, maximum atmospheric pressure drop, and design basis missile characteristics. Recommended values of these parameters are provided. This standard does not address the forces on structures that result from these physical phenomena.


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