Standards Library

1-70 of 70 results for "ANS"

15.12
Title: DESIGN OBJECTIVES FOR AND MONITORING OF SYSTEMS CONTROLLING RESEARCH REACTOR EFFLUENTS (INCORPORATED INTO ANSI/ ANS 15.11-1987)
Organization: ANS
Year: 1977
Status: Inactive
9
Title: GLOSSARY OF TERMS IN NUCLEAR SCIENCE AND TECHNOLOGY (ANSI N1.1-1976) (REVISION OF ANSI N1.1-67)
Organization: ANS
Year: 1976
Status: Inactive
6.4.3
Title: Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials
Organization: ANS
Year: 1991
Status: Inactive
2.12
Title: GUIDELINES FOR COMBINING NATURAL AND EXTERNAL MAN-MADE HAZARDS AT POWER REACTOR SITES
Organization: ANS
Year: 1978
Status: Inactive
57.5
Title: Light Water Reactors Fuel Assembly Mechanical Design and Evaluation
Organization: ANS
Year: 1996
Status: Inactive
56.3
Title: Overpressure Protection of Low Pressure Systems Connected to the Reactor Coolant Pressure Boundary
Organization: ANS
Year: 1977
Status: Inactive
2.11
Title: Guidelines for Evaluating Site-Related Geotechnical Parameters at Nuclear Power Sites
Organization: ANS
Year: 1978
Status: Inactive
7-4.3.2
Title: APPLICATION CRITERIA FOR PROGRAMMABLE DIGITAL COMPUTER SYSTEMS IN SAFETY SYSTEMS OF NUCLEAR POWER GENERATING STATIONS
Organization: ANS
Year: 1982
Status: Inactive
2.9
Title: Evaluation of Ground Water Supply for Nuclear Power Sites
Organization: ANS
Year: 1980
Status: Inactive
2.13
Title: Evaluation of Surface-Water Supplies for Nuclear Power Sites
Organization: ANS
Year: 1979
Status: Inactive
N2.3
Title: IMMEDIATE EVACUATION SIGNAL FOR USE IN INDUSTRIAL INSTALLATIONS (WITHDRAWN)
Organization: ANS
Year: 1979
Status: Inactive
56.4
Title: Pressure and Temperature Transient Analysis for Light Water Reactor Containments
Organization: ANS
Year: 1983
Status: Inactive
INDEX 1976-1985
Title: ANS 1976-1985 INDEX
Organization: ANS
Status: Inactive
N18.7
Title: ADMINISTRATIVE CONTROLS FOR NUCLEAR POWER PLANTS
Organization: ANS
Year: 1972
Status: Inactive
N18.1
Title: Selection and Training of Nuclear Power Plant Personnel
Organization: ANS
Year: 1971
Status: Inactive
57.5 ERTA
Title: Light Water Reactors Fuel Assembly Mechanical Design and Evaluation
Organization: ANS
Year: 2010
Status: Inactive
6.4.3 ERRATUM
Title: Gamma-Ray Attenuation Coefficients and Buildup Factors for Engineering Materials
Organization: ANS
Year: 1991
Status: Inactive
56.8
Title: Containment System Leakage Testing Requirements
Organization: ANS
Year: 2020
Status: Active
N18.5
Title: Earthquake Instrumentation Criteria For Nuclear Power Plants
Organization: ANS
Year: 1974
Status: Inactive
10.4
Title: verification and validation of non-safety-related scientific and engineering computer programs for the nuclear industry
Organization: ANS
Year: 2008
Status: Active
2.17
Title: evaluation of subsurface radionuclide transport at commercial nuclear power plants
Organization: ANS
Year: 2010
Status: Active
2.3
Title: Estimating Tornado, Hurricane, and Extreme Straight Line Wind Characteristics at Nuclear Facility Sites
Organization: ANS
Year: 2011
Status: Active
15.4
Title: Selection and Training of Personnel for Research Reactors
Organization: ANS
Year: 2016
Status: Active
15.11
Title: Radiation Protection at Research Reactor Facilities
Organization: ANS
Year: 2016
Status: Active
57.8
Title: Fuel Assembly Identification
Organization: ANS
Year: 2020
Status: Active
8.14
Title: Use of Soluble Neutron Absorbers in Nuclear Facilities Outside Reactors
Organization: ANS
Year: 2004
Status: Active
6.4
Title: Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants
Organization: ANS
Year: 2006
Status: Active
8.12
Title: Nuclear criticality control and safety of plutonium-uranium fuel mixtures outside reactors
Organization: ANS
Year: 1987
Status: Active
19.10
Title: Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals
Organization: ANS
Year: 2009
Status: Active
53.1
Title: Nuclear Safety Design Process For Modular Helium-Cooled Reactor Plants
Organization: ANS
Year: 2011
Status: Active
2.15
Title: criteria for modeling and calculating atmospheric dispersion of routine radiological releases from nuclear facilities
Organization: ANS
Year: 2013
Status: Active
3.14
Title: Process for Infrastructure Aging Management and Life Extension of Nonreactor Nuclear Facilities
Organization: ANS
Year: 2021
Status: Active
6.4.2
Title: Specification For Radiation Shielding Materials
Organization: ANS
Year: 2006
Status: Active
8.22
Title: Nuclear Criticality Safety Based on Limiting and Controlling Moderators
Organization: ANS
Year: 1997
Status: Active
2.26
Title: Categorization Of Nuclear Facility Structures, Systems, And Components For Seismic Design
Organization: ANS
Year: 2004
Status: Active
55.1
Title: Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants
Organization: ANS
Year: 2021
Status: Active
58.14
Title: Safety And Pressure Integrity Classification Criteria For Light Water Reactors
Organization: ANS
Year: 2011
Status: Active
8.26
Title: criticality safety engineer training and qualification program
Organization: ANS
Year: 2007
Status: Active
2.10
Title: Criteria for Retrieval, Processing, Handling, and Storage of Records from Nuclear Facility Seismic Instrumentation
Organization: ANS
Year: 2017
Status: Active
2.21
Title: Criteria for Assessing Atmospheric Effects on the Ultimate Heat Sink
Organization: ANS
Year: 2022
Status: Active
3.2
Title: Managerial, administrative, and quality assurance controls for the operational phase of nuclear power plants
Organization: ANS
Year: 2012
Status: Active
19.11
Title: Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Pressurized Water Reactors
Organization: ANS
Year: 2017
Status: Active
RA-S-1.1
Title: Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications
Organization: ANS
Year: 2022
Status: Active
8.7
Title: Nuclear Criticality Safety in the Storage of Fissile Materials
Organization: ANS
Year: 2022
Status: Active
30.3
Title: Light Water Reactor Risk-Informed, Performance-Based Design
Organization: ANS
Year: 2022
Status: Active
19.4
Title: A Guide for Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification
Organization: ANS
Year: 2017
Status: Active
19.3.4
Title: The Determination of Thermal Energy Deposition Rates in Nuclear Reactors
Organization: ANS
Year: 2022
Status: Active
8.6
Title: Safety in Conducting Subcritical Neutron-Multiplication Measurements in Situ
Organization: ANS
Year: 1983
Status: Active
8.3
Title: Criticality Accident Alarm System
Organization: ANS
Year: 2022
Status: Active
15.21
Title: Format and Content for Safety Analysis Reports for Research Reactors
Organization: ANS
Year: 2012
Status: Active
2.6
Title: Guidelines IRU Estimating Present & Projecting Future Population Distributions Surrounding Nuclear Facility Sites
Organization: ANS
Year: 2018
Status: Active
10.5
Title: Accommodating User Needs In Scientific And Engineering Computer Software Development
Organization: ANS
Year: 2006
Status: Active
15.2
Title: Quality Control for Plate-Type Uranium-Aluminum Fuel Elements
Organization: ANS
Year: 1999
Status: Active
5.4
Title: Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel
Organization: ANS
Year: 2011
Status: Active
8.24
Title: Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations
Organization: ANS
Year: 2017
Status: Active
57.3
Title: Design Requirements for New Fuel Storage Facilities at Light Water Reactor Plants
Organization: ANS
Year: 2018
Status: Active
58.16
Title: Safety Categorization and Design Criteria for Nonreactor Nuclear Facilities
Organization: ANS
Year: 2014
Status: Active
19.3
Title: Steady-State Neutronics Methods for Power Reactor Analysis
Organization: ANS
Year: 2022
Status: Active
8.5
Title: Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material
Organization: ANS
Year: 1996
Status: Inactive
10.7
Title: Non-real-time, High-integrity Software for the Nuclear Industry-Developer Requirements
Organization: ANS
Year: 2013
Status: Active
15.1
Title: The development of technical specifications for research reactors
Organization: ANS
Year: 2007
Status: Active
6.1.2
Title: group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear power plants
Organization: ANS
Year: 2013
Status: Active
8.21
Title: Use of Fixed Neutron Absorbers in Nuclear Facilities Outside Reactors
Organization: ANS
Year: 2023
Status: Active
3.4
Title: Medical certification and monitoring of personnel requiring operator licenses for nuclear power plants
Organization: ANS
Year: 2013
Status: Active
8.1
Title: Nuclear criticality safety in operations with fissionable materials outside reactors
Organization: ANS
Year: 2014
Status: Active
41.5
Title: Verification and Validation of Radiological Data for Use in Waste Management and Environmental Remediation
Organization: ANS
Year: 2012
Status: Active
15.8
Title: Quality assurance program requirements for research reactors
Organization: ANS
Year: 1995
Status: Active
16.1
Title: Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure
Organization: ANS
Year: 2019
Status: Active
19.1
Title: Nuclear Data Sets for Reactor Design Calculations
Organization: ANS
Year: 2019
Status: Active
20.2
Title: Nuclear Safety Design Criteria and Functional Performance Requirements for Liquid-Fuel Molten Salt Reactor Nuclear Power Plants
Organization: ANS
Year: 2023
Status: Active


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