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: [email protected] or 1-212-642-4980 or Request Proposal Price.
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ANSI/ANS-3.5-2018
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-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-6.1.1-2020
Photon and Neutron Fluence-to-Dose Conversion Coefficients
This standard presents data recommended for computing the biologically relevant dosimetric quantity in photon and neutron radiation fields. Specifically, this standard is intended for use by radiation shielding designers for the calculation of effective dose. Fit coefficients are given for evaluating whole-body effective dose per unit fluence for photons with energy 10 keV to 10 GeV and for neutrons with energy 0.001 eV to 10 GeV. Eight different irradiation geometries are considered. Establishing exposure limits is outside the scope of this standard.
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.
ANSI/ANS-2.29-2020
Probabilistic Seismic Hazard Analysis
This standard provides guidance for performing a probabilistic seismic hazard analysis (PSHA) for developing design and safety evaluation criteria for nuclear facilities. Criteria provided in this standard address various aspects of conducting PSHAs, including (1) purpose, objective, and process; (2) detailed requirements; (3) PSHA framework; (4) seismic source model; (5) ground motion model; (6) site effects; (7) implementation of PSHA for seismic design and seismic probabilistic risk assessment; (8) documentation; (9) quality assurance.
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-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-15.21-2012 (R2018)
Format and Content for Safety Analysis Reports for Research Reactors
This standard provides the criteria for the format and content for safety analysis reports (SARs) for research reactors.
ANSI/ANS-16.1-2019
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-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).
