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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 19.1: nuclear data sets for reactor design calculations
Abstract: General
This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include ~a! ...
This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include ~a! ...
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 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 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 57.1: Design Requirements for Light Water Reactor Fuel Handling Systems
Abstract: This standard sets forth the required functions of fuel handling systems at light water reactor nuclear power plants.
It provides minimum design requirements for equipment and tools to handle nuclear fuel and control ...
It provides minimum design requirements for equipment and tools to handle nuclear fuel and control ...
ANS 55.4: Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants
Abstract: This standard sets forth minimum design, construction, and performance requirements, with due consideration for operation, for gaseous radioactive waste processing systems(GRWPS) for light water reactor(LWR) plants. It is ...
ANS 8.5: Use of borosilicate-glass Raschig rings as a neutron absorber in solutions of fissile material
Abstract: This standard provides guidance for the use of borosilicate-glass Raschig rings as a neutron absorber for criticality control in ring-packed vessels containing solutions of 235U, 239Pu, or 233U. ...
ANS 6.1.2: Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
Abstract: This standard specifies neutron amd gamma-ray cross sections and related group-avaraged or derived data for the energy range and materials of importance in nuclear radiation protection and shielding calculations for nuclear ...