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ANS 55.1: Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants
Abstract: This standard sets forth the design, construction, and performance requirements for a solid radioactive waste processing system for light-water-cooled reactor plants. For the purposes of this standard, the solid radioactive ...
ANS 2.27: criteria for investigations of nuclear facility sites for seismic hazard assessments
Abstract: This standard provides criteria and guidelines for conducting geological, seismological, and geotechnical investigations needed to provide information to support the following:
(1)Seismic source characterization input ...
(1)Seismic source characterization input ...
ANS 51.10: Auxiliary feedwater system for pressurized water reactors
Abstract: This standard sets forth the nuclear safety-related functional requirements, performance requirements, design criteria, design requirements for testing and maintaince, and interfaces for the nuclear safety-related portion ...
ANS 58.8: Time Response Design Criteria for Safety-Related Operator Actions
Abstract: This standard establishes time response design criteria for safety-related operator actions to be used in the design of light water reactor (LWR) nuclear power plants. The criteria are used to determine the minimum response ...
ANS 5.4: Method for calculating the fractional release of volatile fission products from oxide fuel
Abstract: Scope and purpose
This standard provides an analytical method for calculating the release of volatile fission products from uranium dioxide(UO2) fuel pellets during normal reactor operation. When used with nuclide yields, this method will give the release-to-birth ratio R/B or the so-called "gap release," which is th...
This standard provides an analytical method for calculating the release of volatile fission products from uranium dioxide(UO2) fuel pellets during normal reactor operation. When used with nuclide yields, this method will give the release-to-birth ratio R/B or the so-called "gap release," which is th...
ANS 2.21: Criteria for Assessing Atmospheric Effects on the Ultimate Heat Sink
Abstract: This standard describes atmospheric effects for consideration when designing ultimate heat sinks for safety-related systems at nuclear power units. Required analyses are provided for a meteorological assessment of the ...
ANS 41.5: verification and validation of radiological data for use in waste management and environmental remediation
Abstract: This standard establishes criteria and processes for verification and validation of radioanalytical data for waste management and environmental remediation activities. It applies to the independent review of the data ...
ANS 6.4.2: Specification for Radiation Shielding Materials
Abstract: This standard sets forth physical and nuclear properties that shall be reported by the supplier as appropriate for a particular application in order to form the basis for the selection of radiation shielding materials.
ANS 14.1: Operation of Fast Pulse Reactors
Abstract: 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 ...
ANS 58.3: Physical Protection for Nuclear Safety-Related Systems and Components
Abstract: This standard sets forth physical protection criteria for nuclear safety-related systems and components in stations using light water reactors (LWRs). This standard includes identification of potential hazards to nuclear ...

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