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ANS > Standards > Get Involved > Volunteer Opportunities > N17 > ANS-6 |
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ANS-6, Radiation Protection and Shielding If you are interested in participating in the following standards, complete and submit the Standards Volunteer Form. ANS-6.1.1, Neutron and Gamma-Ray Fluence-To-Dose Factors  Scope: This standard presents data recommended for computing the biologically relevant dosimetric quantity in neutron and gamma-ray radiation fields. Specifically, this standard is intended for use by shield designers to calculate effective dose equivalent. Values are given for effective dose equivalent per unit fluence for neutron energies from 1eV to 14 MeV and for gamma-ray energies from 0.01 to 12 MeV. Establishing maximum permissible exposure limits is outside the scope of this standard. ANS-6.1.2, Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants Scope: This standard provides information on acceptable evaluated nuclear data and group-aveaged neutron and gamma-ray cross section libraries derived from these evaluated nuclear data based on the energy range and materials of importance in nuclear radiation protetion and shielding calculations for nuclear power plants. ANS-6.3.1, Program for Testing Radiation Shields in Light Water Reactors (LWR) Scope: This standard describes a test program to be used in evaluating biological radiation shielding in nuclear reactor facilities under normal operating conditions including anticipated operational occurrences. The program encompasses examining and testing to be performed before startup, during startup, and testing subsequent to the startup phase. Post startup tests are required for the shielded components which do not contain sufficient radioactivity during the startup phase to allow valid testing. Shielding of these components is to be tested when radiation sources develop or are introduced into sufficient strength to allow meaningful measurements. Post startup shield tests are also required whenever radioactive or potentially radioactive equipment which could affect the adequacy of the installed shielding is introduced into the plant or relocated within the plant, or when previously tested shielding has been modified. One special category of post start-up testing is the testing of shielding during refueling operations. ANS-6.4, Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants Scope: The standard contains methods and data needed in design of concrete shielding required for protection of personnel and equipment against the effects of gamma rays and neutrons. Specific guidance is given regarding attenuation calculations, shielding design, and standards of documentation. ANS-6.4.2, Specification for Radiation Shielding Materials Scope: 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-6.6.1, Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plants Scope: This standard defines calculational requirements and discusses measurement techniques for estimates of dose rates near light water reactor (LWR) nuclear power plants due to direct and scattered gamma-rays from contained sources onsite. Onsite locations outside plant buildings and locations in the offsite unrestricted area are considered. All sources that contribute significantly to dose rates are identified and methods for calculating the source strength of each are discussed. Particular emphasis is placed on 16N sources as they are significant sources of direct and scattered radiation for boiling water reactors (BWR). The standard specifically excludes radiation from gaseous and liquid effluents. The standard describes the considerations necessary to compute dose rates, including component self-shielding, shielding afforded by walls and structures, and scattered radiation. The requirements for measurements and data interpretation of measurements are given. The standard includes normal operation and shutdown conditions but does not address accident or normal operational transient conditions. |
