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ANS > Standards > Get Involved > Volunteer Opportunities > NFSC > ANS-24 |
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ANS-24, Modeling and Analysis If you are interested in participating in the following standards, complete and submit the Standards Volunteer Form. ANS-2.15, Criteria for Modeling and Calculating Atmospheric Transport of Routine Releases from Nuclear Facilities  Scope: This standard establishes criteria for use of meteorological data collected at nuclear facilities to evaluate the atmospheric effects on routine radioactive releases, inclusive of dilution, dispersion, plume rise, plume meander, aerodynamic effects of buildings, dry, deposition, and wet deposition (e.g., precipitation scavenging). ANS-2.16, Criteria for Modeling Design-Basis Accidental Releases from Nuclear Facilities Scope: This standard established criteria for use of meteorological data collected at nuclear facilities to evaluate the atmospheric effects on accidental radioactive and chemical releases, inclusive on dilution, dispersion, plume rise, plume meander, aerodynamic effects of buildings, dry deposition, and wet deposition (e.g., precipitation scavenging). These criteria may also be useful in Department of Homeland Security (DHS) consequence assessments. ANS-2.29, Probabilistic Seismic Hazard Analysis Scope: This standard provides criteria to establish the probabilistic basis for various levels of natural phenomena hazards at nuclear materials facility sites ANS-3.8.5, Criteria for Emergency Radiological Field Monitoring, Sampling and Analysis Scope: This standard provides criteria for the Emergency Radiological Field Monitoring Program, which establishes the approach to field monitoring, sampling, and analysis during and after an emergency. It addresses the issues relative to the field monitoring team: 1) organization, staffing, and training, 2) equipment and supplies, 3) procedures and techniques, 4) and sample analysis. This standard does not include either routine environmental monitoring programs used to establish baseline environmental conditions or dose assessment programs. ANS-3.8.10, Criteria for Modeling Real-time Accidental Release Consequences at Nuclear Facilities Scope: This standard establishes criteria for use of meteorological data collected at nuclear facilities or nearby stations to evaluate in real time the atmospheric effects on all anticipated accidental radioactive and hazardous chemical releases during emergencies, inclusive of atmospheric transport and dispersion ANS-5.4, Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel Scope: This standard provides an analytical method for calculating the release of volatile fission products from oxide fuel pellets during normal reactor operation. When used with nuclide yields, this method will give the so-called "gap activity," which is the inventory of volatile fission products that could be available for release from the fuel rod if the cladding were breached. The standard considers high-temperature (up to the melting point) and low-temperature (where temperature-independent processes dominate) releases and distinguishes between short-halflife (halflife less than one year) and long-halflife (halflife greater than one year) nuclides. This standard requires that releases for nuclides of interest be calculated with both the high-temperature and the low-temperature models, and the larger of the two calculated releases is to be taken as the result. ANS-5.10, Airborne Release Fractions at Non-Reactor Nuclear Facilities Scope: This standard provides criteria for defining Airborne Release Fractions (ARFs) for radioactive materials under accident conditions (excluding nuclear criticalities) at non-reactor nuclear facilities. The criteria in this standard provide requirements for selecting ARFs based on the calculated or assumed forms of radioactive material released. This standard may be applied to determine the ARFs for certain applicable reactor plant events for which alternative methodologies are not mandated by regulatory requirements. Because the predominant physical forms of radioactive materials in non-reactor facilities are solids and liquids, the standard focuses on these forms. Criteria are also provided for gases and materials that can be converted into the form of a vapor. ANS-16.1, Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure Scope: This standard, ANSI/ANS-16.1-2003, 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 waste-form development field. It contains the provisions published in the original version of this standard in 1986. ANS-18.1, Radioactive Source Term for Normal Operation of Light Water Reactors Scope: This standard provides a set of typical radionuclide concentrations for estimating the radioactivity in the principal fluid systems of light water reactors and for projecting the expected releases of radioactivity from nuclear plants. It is not Intended that the values be used as the sole basis for design, but be used in environmental reports and elsewhere where expected operating conditions over the life of the plant would be appropriate. ANS-41.5, Verification and Validation of Radiological Data for Use in Waste Management and Environmental Remediation Scope: This standard establishes criteria and processes for determining the validity of radioanalytical data for waste management and environmental remediation. These applications include site characterization, waste acceptance, waste certification, waste treatment design, process control, risk communication, litigation, and other applications as deemed necessary. ANS-58.2, Design Basis for Protection of Light Water Nuclear Power Plants Against the Effects of Postulated Pipe Rupture Scope: This standard addresses the design basis for the protection of light water reactor nuclear power plants from the potentially adverse effects of postulated pipe ruptures. |
