Standards
| ANSI/ANS-8.1: Nuclear Criticality Safety in Operations with Fissionable Materials 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 U-233, U-235, Pu-239, 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. 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. | ||
| Current Version: ANS-8.1-2014 (R2023) | Chair: N. Brown (nwbrown@bwxt.com) | |
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ANSI/ANS-8.3: Criticality Accident Alarm System | ||
| 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. | ||
| Current Version: ANS-8.3-2022 |
Chair: J. Hicks (jerryhicks@aol.com) | |
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ANSI/ANS-8.6: Safety in Conducting Subcritical Neutron-Multiplication Measurements In Situ | ||
| This standard provides safety guidance for conducting subcritical neutron-multiplication measurements where physical protection of personnel against the consequences of a criticality accident is not provided. The objectives of in situ measurements are either to confirm an adequate safety margin or to improve an estimate of such a margin. The first objective may constitute a test of the criticality safety of a design that is based on calculations. The second may affect improved operating conditions by reducing the uncertainty of safety margins and providing guidance to new designs. | ||
| Current Version: ANS-8.6-1983 (R2022) |
Chair: T. Cutler (tcutler@lanl.gov) | |
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ANSI/ANS-8.7: Guide for Nuclear Criticality Safety in the Storage of Fissile Materials | ||
| This standard is applicable to the storage of fissile materials. Mass and spacing limits are tabulated for uranium containing greater than 30 wt-% U-235, for U-233, and for plutonium, as metals and oxides. Criteria for the range of application of these limits are provided. | ||
| Current Version: ANS-8.7-2022 |
Chair: J. Kuropatwinski (wujek@lanl.gov) | |
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ANSI/ANS-8.10: Criteria for Nuclear Criticality Safety Controls in Operations with Shielding and Confinement | ||
| This standard is applicable to operations outside of nuclear reactors with U-235, U-233, Pu-239, and other fissionable materials in which shielding and confinement are provided for protection of personnel and the public. Criteria are provided that may be used for criticality safety controls under these conditions. This standard does not apply to the assembly of these materials under controlled conditions, such as in critical experiments. This standard does not include the details of administrative procedures for control, which are considered to be management prerogatives, details regarding the design of processes and equipment, or descriptions of instrumentation for process control. | ||
| Current Version: ANS-8.10-2015 (R2020) |
Chair: A. Prichard (andrewwprichard@gmail.com) | |
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ANSI/ANS-8.12: Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures Outside Reactors | ||
| This standard is applicable to operations with plutonium-uranium oxide fuel mixtures outside nuclear reactors, except the assembly of these materials under controlled conditions, such as in critical experiments. Basic criteria are presented for plutonium-uranium fuel mixtures in single units of simple shape containing no more than 30 wt-% plutonium combined with uranium containing no more than 0.71 wt-& U-235. | ||
| Current Version: ANS-8.12-1987 (R2021) |
Chair: T. Stover (stover.tracy@gmail.com) | |
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ANSI/ANS-8.14: Use of Soluble Neutron Absorbers in Nuclear Facilities Outside Reactors | ||
| This standard provides guidance for the use of soluble neutron absorbers for criticality control. This standard addresses neutron absorber selection, system design and modifications, safety evaluations, and quality control programs. | ||
| Current Version: ANS-8.14-2004 (R2021) |
Chair: K. Wessels (kristan.wessels@cns.doe.gov) | |
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ANSI/ANS-8.15: Nuclear Criticality Control of Selected Actinide Nuclides | ||
| This standard is applicable to operations with the following nuclides: U-232, U-234, Np-237, Pu-236, Pu-238, Pu-240, Pu-241, Pu-242, Am-241, Am-242m, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cf-249, and Cf-251. Subcritical mass limits are presented for isolated units. These limits are not applicable to interacting units. | ||
| Current Version: ANS-8.15-2014 (R2024) |
Chair: C. Rombough (romboweb@ctr-tech.com) | |
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ANSI/ANS-8.17: Criticality Safety Criteria for the Handling, Storage, and Transportation of LWR Fuel Outside Reactors | ||
| This standard provides nuclear criticality safety criteria for the handling, storage, and transportation of light water reactor fuel rods and units outside reactors cores. | ||
| Current Version: ANS-8.17-2004 (R2019) |
Chair: A. Lang (langa@ornl.gov) E. Saylor (emsaylor@comcast.net) |
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ANSI/ANS-8.19: Administrative Practices for Nuclear Criticality Safety | ||
| This standard provides criteria for the administration of a nuclear criticality safety program for operations with fissile materials outside of nuclear reactors in which there exists a potential for nuclear criticality accidents. This standard addresses the responsibilities of management, supervision, and nuclear criticality safety staff. It also addresses operating procedures, nuclear criticality safety evaluations, and materials control. | ||
| Current Version: ANS-8.19-2014 (R2019) |
Chair: John Miller (millerj@sandia.gov) | |
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ANSI/ANS-8.20: Nuclear Criticality Safety Training | ||
| This standard provides criteria for nuclear criticality safety training for personnel associated with operations outside reactors where a potential exists for criticality accidents. It is not sufficient for the training of nuclear criticality safety staff. | ||
| Current Version: ANS-8.20-1991 (R2020) |
Chair: D. Hill (deborah.a.hill@uknnl.com) | |
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ANSI/ANS-8.21: Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors | ||
| This standard provides guidance for the use of fixed neutron absorbers as an integral part of nuclear facilities and fissionable material process equipment outside reactors, where such absorbers provide criticality safety control. | ||
| Current Version: ANS-8.21-2023 |
Chair: D. Erickson (dg_erickson@bluehorn.us) | |
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ANSI/ANS-8.22: Nuclear Criticality Safety Based on Limiting and Controlling Moderators | ||
| This standard applies to limiting and controlling moderators to achieve criticality safety in operations with fissile materials in a moderator control area. This standard does not apply to concentration control of fissile materials. | ||
| Current Version: ANS-8.22-1997 (R2021) |
Chair: M. Crouse (michael.crouse@cns.doe.gov) L. Paulson (lon.paulson@ge.com) |
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ANSI/ANS-8.23: Nuclear Criticality Accident Emergency Planning and Response | ||
| This standard provides criteria for minimizing risks to personnel during emergency response to a nuclear criticality accident outside reactors. This standard applies to those facilities for which a criticality accident alarm system, as specified in American National Standard Criticality Accident Alarm System, ANSI/ANS-8.3, is in use. This standard does not apply to nuclear power plant sites or to licensed research reactor facilities, which are addressed by other standards. | ||
| Current Version: ANS-8.23-2019 |
Chair: B. O'Donnell (odonnell.brandon@gmail.com) | |
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ANSI/ANS-8.24: Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations | ||
| This standard provides requirements and recommendations for validation, including establishing applicability, of neutron transport calculational methods used in determining critical or subcritical conditions for nuclear criticality safety analyses. | ||
| Current Version: ANS-8.24-2017 (R2023) |
Chair: L. Wetzel (llwetzel@verizon.net) | |
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ANSI/ANS-8.26: Criticality Safety Engineer Training and Qualification Program | ||
| This standard presents the fundamental content elements of a training and qualification program for individuals with responsibilities for performing the various technical aspects of criticality safety engineering. The standard presents a flexible array of competencies for use by management to develop tailored training and qualification programs applicable to site-specific job functions, facilities, and operations. | ||
| Current Version: ANS-8.26-2007 (R2022) |
Chair: K. Reynolds (kevin.reynolds@pxy12.doe.gov) | |
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ANSI/ANS-8.27: Burnup Credit for LWR Fuel | ||
| This standard provides criteria for accounting for reactivity effects of fuel irradiation and radioactive decay in criticality safety control of storage, transportation, and disposal of commercial LWR UO2 fuel assemblies. | ||
| Current Version: ANS-8.27-2015 (R2020) |
Chair: B.J. Marshall (marshallwj@ornl.gov) | |
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ANSI/ANS-8.28: Administrative Practices for the Use of Non-Destructive Assay Measurements for Nuclear Criticality Safety | ||
| This standard provides administrative practices covering the interface between the criticality safety community and the NDA community including in-situ measurements and measurements of containerized materials. | ||
| Current Version: ANS-8.28-2024 |
Chair: J. Chapman (jeffrey.chapman@nnsa.doe.gov) E. Elliott (reformed_one@hotmail.com) |
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Last modified December 11, 2024, 11:30am CST