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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: or 1-212-642-4980 or Request Proposal Price.

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ANSI/ANS-15.8-1995 (R2018)

Quality Assurance Program Requirements for Research Reactors

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


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

This standard provides a procedure to measure and index the release rates of non-volatile radionuclides from low-level radioactive waste forms in demineralized water over a test period. It can be applied to any material from which test specimens can be prepared by casting or cutting into a shape for which the surface area and volume can be determined. The results of this procedure do not represent waste form degradation in any specific environmental situation or represent waste form performance. The test method presented in this standard is an adaptation of the method published in the 1986 version of this standard but constrains test parameter values and data analyses to support direct comparisons of test responses of different waste form materials.

ANSI/ANS-8.1-2014 (R2018)

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-8.3-1997 (R2017)

Criticality Accident Alarm System

"R" in the numeric designation signifies that the 1997 standard was reaffirmed (recertified) as an American National Standard in 2003 & 2012. No changes can be made to a standard during reaffirmation.This standard is applicable to all operations involving fissionable materials in which inadvertent criticality can occur and cause personnel to receive unacceptable exposure to radiation. This standard is not applicable to detection of criticality events where no excessive exposure to personnel is credible, nor to nuclear reactors or critical experiments. This standard does not include details of administrative actions or of emergency response actions that occur after alarm activation.


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-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-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.

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.


Nuclear Power Plant Simulators for Use in Operator Training and Examination

This standard establishes the functional requirements for full-scope nuclear power plant control room simulators that are subject to U.S. Nuclear Regulatory Commission regulation for use in operator training and examination. This standard also establishes criteria for the scope of simulation, performance, and functional capabilities of nuclear power plant control room simulators.  This standard does not establish criteria for the use of simulators in training programs.

ANSI/ANS-2.23-2016 (R2020)

Nuclear Power Plant Response to an Earthquake

This standard describes actions that the owner of a nuclear power plant shall take to prepare for and respond to a felt earthquake at the plant(s), including the need for plant shutdown; actions to determine the readiness of the plant to resume operation; and those evaluations necessary to verify the long-term integrity of safety-related and important structures, systems, and components. It also includes a consensus definition of operating basis earthquake exceedance, beyond which U.S. regulations require plant shutdown. Application of this revised standard provides a comprehensive, balanced plan for the response of a nuclear power plant to an earthquake.


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