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ANS - American Nuclear Society: Recent submissions
Now showing items 61-80 of 87
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ANS 19.3
Abstract: This standard provides guidance for performing and validating the sequence of steady-state calculations leading to prediction—in all types of operating commercial nuclear reactors—of the following:
(1) ... -
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 3.2
Abstract: Scope and applicability
This standard provides requirements and recommendations for managerial and administrative controls to ensure that activities associated with operating a nuclear power plant are ... -
ANS 19.3.4
Abstract: It is the purpose of this standard to provide criteria for the following:
(1) determination of the energy allocation among the principal particles and photons produced in fission, both prompt and delayed;
(2) ... -
ANS 10.2
Abstract: This standard provides recommended programming practices and requirements to facilitate the portability of computer programs prefared for scientific and engineering computations. -
ANS 15.21
Abstract: This standard provides the criteria for the format and content for safety analysis reports ~SARs! for research reactors.
Purpose
Research reactors require safety analysis and documentation showing ... -
ANS 59.52
Abstract: This standard provides functional, performance, and design requirements for lubricating oil systems for diesel genarartors that provide emergency onsite power for light water reactor nuclear power plants. The standard ... -
ANS 19.6.1
Abstract: This standard applies to the reactor physics tests that are performed following a refueling or other core alteration of a PWR for which nuclear design calculations are required. This standard does not address the physics ... -
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 19.10
Abstract: This standard provides a procedure for the evaluation of the best-estimate fast (E > 1.0 MeV) neutron fluence in the annular region between the core and the inside surface of the vessel, through the pressure vessel ... -
ANS 8.24
Abstract: This standard provides requirements and recommendations for validation, including establishing applicability, of neutron transport calculational methods used in determining critical or subcritical conditions for nuclear ... -
ANS 14.1
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 10.4
Abstract: This standard provides guidelines for the verification and validation ~V&V! of non-safetyrelated scientific and engineering computer programs developed for use by the nuclear industry. The scope is restricted to research ... -
ANS 59.51
Abstract: This standard provides functional, performance, and initial design requirements for the fuel oil system for diesel generators that provide safety-related emergency onsite power for light water reactor nuclear power plants. ... -
ANS 16.1
Abstract: This standard ANSI/ANS-16.1-2003,1) provides a unform procedure to measure and index the release of radionuclides from waste forms as a result of leaching in demineralised water for 5 days.2) The ... -
ANS 58.3
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 ... -
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 ...