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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-10.2-2000 (R2009)

Portability of Scientific and Engineering Software

This standard provides recommended programming practices and requirements to facilitate the portability of computer programs prepared for scientific and engineering computations.


ANSI/ANS-3.1-2014

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-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-10.5-2006 (R2016)

Accommodating User Needs in Scientific and Engineering Computer Software Development

This standard presents criteria for accommodating user needs in the preparation of computer software for scientific and engineering applications.


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-2.26-2004 (R2010)

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-14.1-2004 (R2014)

Operation of Fast Pulse Reactors

This standard is for those involved in the design, operation, and review of fast pulse reactors. It has been formulated in general terms to be applicable to all current fast pulse reactors. This standard does not apply to periodically pulsed reactors or booster assemblies.


ANSI/ANS-15.11-2016

Radiation Protection at Research Reactor Facilities

This standard establishes the elements of a radiation protection program and the criteria necessary to provide an acceptable level of radiation protection for personnel at research reactor facilities and the public consistent with keeping exposures and releases as low as is reasonably achievable (ALARA).


ANSI/ANS-15.1-2007 (R2013)

The Development of Technical Specifications for Research Reactors

This standard identifies and establishes the content of technical specifications for research and test reactors. Areas addressed are: Definitions, Safety Limits, Limiting Safety System Settings,Limiting Conditions for Operation, Surveillance Requirements, Design Features, and Administrative Controls. Sufficient detail is incorporated so that applicable specifications can be derived or extracted.


ANSI/ANS-15.4-2016

Selection and Training of Personnel for Research Reactors

This standard provides criteria for the selection and training of research reactor operating personnel. It addresses their qualifications, training, initial licensing, requalification, and relicensing. This standard is predicated on levels of responsibility rather than on a particular organizational concept.


ANSI/ANS-16.1-2003 (R2008)

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

This standard provides a uniform procedure to measure and index the release of radionuclides from waste forms as a result of leaching in demineralized water for 5 days. The results of this procedure do not apply to any specific environmental situation except through correlative studies of actual disposal site conditions. The test presented in this standard has much in common with the original International Atomic Energy Agency proposal and has by now become familiar to those working in the radioactive wasteform development field. It contains the provisions published in the original version of this standard in 1986.


ANSI/ANS-2.29-2008 (R2016)

Probabilistic Seismic Hazard Analysis

This standard provides criteria and guidance for performing a Probabilistic Seismic Hazard Analysis (PSHA) for the design and construction of nuclear facilities. As defined in ANSI/ANS-2.26-2004, a nuclear facility is a facility that stores, processes, tests, or fabricates radioactive materials in such form and quantity that a nuclear risk to the workers, to the off-site public, or to the environment may exist. These include, but are not limited to, nuclear fuel manufacturing facilities; nuclear material waste processing, storage, fabrication, and reprocessing facilities; uranium enrichment facilities; tritium production and handling facilities; radioactive materials laboratories; and nuclear reactors. Criteria provided in this standard address various aspects of conducting PSHAs, including:1. Selection of the process, methodology and the level of seismic hazard analysis appropriate for a given Seismic Design Category (SDC) structure, system, or component (SSC) or facility (hereafter, the SDC of a facility is considered synonymous with the highest SDC SSC in the facility) and the geotechnical and seismological characteristics of the site;2. Seismic sources characterization;3. Ground motion estimation;4. Site response assessment;5. Assessment of aleatory and epistemic uncertainties in a PSHA;6. PSHA documentation requirements;This standard does not specify methods for estimating the probability of fault displacement, or other seismically induced hazards such as soil liquefaction, soil settlement, land sliding, and earthquake-induced flooding. These hazards may be applicable for certain sites and need to be evaluated and included in SSC design requirements. Methods for doing this are included in ANSI/ASCE/SEI 43-05.This standard does not address criteria, procedures or methods for collecting information and data required to perform a PSHA. These are specified in ANSI/ANS-2.27-2008, +GΘ╝+⌠Criteria for Investigations of Nuclear Facility Sites for Seismic Hazard Assessments.+GΘ╝-Ñ In addition, this standard does not address the use of PSHA results or the selection of design basis earthquakes (DBEs) for nuclear facilities. This topic is covered in ANSI/ANS-2.26-2004 and ANSI/ASCE/SEI 43-05. The use of this standard shall be coordinated with the other three seismic standards named above. This coordination is vital to the collection and evaluation of data required to perform the PSHA, to establish the level and scope of the analysis consistent with an application, and for consistency with the intended use of the PSHA results. The guidelines and requirements provided in this standard are applicable for the design and evaluation of SDC 3, 4, and 5 facilities. These can also be applied to SDC 1 and 2, or other non-DOE facilities if, for safety, economy, or other reasons, a site-specific seismic hazard determination becomes necessary.


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.


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