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Browsing ANS - American Nuclear Society by Issue Date
Now showing items 1-20 of 87
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ANS 58.11
Abstract: This standard provides design criteria for systems that perform the safety-related functions necessary to shut down a reactor and maintain it in a safe shutdown condition for selected design basis events; i.e., any design ... -
ANS 2.10
Abstract: This standard provides criteria for the timely retrieval and the subsequent processing, handling, and storage of data obtained from seismic instrumentation specified in ANSI/ANS-2.2- 2002 [1].1) Also included ... -
ANS 57.1
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 ... -
ANS 8.19
Abstract: This standard provides criteria for the administration of a nuclear criticality safety program for outside-of-reactor operations in which there exists a potential for nuclear criticality accidents.
Responsibilities of ... -
ANS 8.10
Abstract: This standard is applicable to operations outside of nuclear reactors with 235U, 233U, 239Pu, and other fissile and fissionable materials in which shielding and confinement are provided ... -
ANS 8.15
Abstract: This standard is applicable to operations with the following:
23793NP, 23894Pu, 24194Pu, 24294Pu,24195Am, ... -
ANS 3.11
Abstract: This document provides criteria for gathering and assembling meteorological information at commercial nuclear electric generating stations, U.S Department of Energy/National Nuclear Security Administration nuclear facilities, ... -
ANS 8.20
Abstract: 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 ... -
ANS 5.1
Abstract: This standard sets forth values for the decay heat power from fission products and 239U and 239Np following shutdown of light water reactors (LWRs) containing 235U, 238U, and plutonium. The decay heat power from fission ... -
ANS 6.4.2
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 6.4
Abstract: This standard contains methods and data needed to calculate the concrete thickness required for radiation shielding in nuclear power plants. Where possible, specific recommendations are made regarding radiation attenuation ... -
ANS 57.5
Abstract: This standard sets forth a series of design conditions and functional requirements for the design of fuel assemblies for light water cooled commercial power reactors. It includes specific requirements for design, as well ... -
ANS 6.6.1
Abstract: 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 ... -
ANS 55.4
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
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 6.3.1
Abstract: 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 occurances. The program ... -
ANS 15.4
Abstract: This standard provides criteria for the selection and training of research reactor operating personnel. It addresses their qualifications, training, initial licensing, requalification, and relicensing.
This standard ... -
ANS 8.7
Abstract: This stanadard is applicable to the storage of fissile materials. Mass and spacing limits are tabulated for uranium containing greater than 30 wt-% 235U, for 233U, and for plutonium, as matals and ...