ANS - Historical - 1986-1996 Collection
This collection contains documents from the following standards organization(s): American Nuclear Society 1 2 > >
| ANS 1 | EN-SAFETY GUIDE FOR THE PERFORMANCE OF CRITICAL EXPERIMENTS (ANSI N405-1975) (R 1981) | |
| ANS 10.2 | EN-Portability of Scientific and Engineering Software | |
| ANS 10.2 | EN-RECOMMENDED PROGRAMMING PRACTICES TO FACILITATE THE PORTABILITY OF SCIENTIFIC COMPUTER PROGRAMS | |
| ANS 10.3 | EN-GUIDELINES FOR THE DOCUMENTATION OF DIGITAL COMPUTER PROGRAMS | |
| ANS 10.3 | EN-GUIDELINES FOR THE DOCUMENTATION OF DIGITAL COMPUTER PROGRAMS | |
| ANS 10.4 | EN-Guidelines for the verification and validation of scientific and engineering computer programs for the nuclear industry | |
| ANS 10.5 | EN-GUIDELINES FOR CONSIDERING USER NEEDS IN COMPUTER PROGRAM DEVELOPMENT | |
| ANS 10.5 | EN-GUIDELINES FOR CONSIDERING USER NEEDS IN COMPUTER PROGRAM DEVELOPMENT | |
| ANS 14.1 | EN-Operation of Fast Pulse Reactors | |
| ANS 15.1 | EN-Development of technical specifications for research reactors | |
| ANS 15.1 | EN-DEVELOPMENT OF TECHNICAL SPECIFICATIONS FOR RESEARCH REACTORS | |
| ANS 15.10 | EN-DECOMMISSIONING OF RESEARCH REACTORS (R 1987) | |
| ANS 15.11 | EN-RADIATION PROTECTION AT RESEARCH REACTOR FACILITIES | |
| ANS 15.11 | EN-RADIOLOGICAL CONTROL AT RESEARCH REACTOR FACILITIES | |
| ANS 15.11 | EN-Radiation protection at research reactor facilities | |
| ANS 15.12 | EN-DESIGN OBJECTIVES FOR AND MONITORING OF SYSTEMS CONTROLLING RESEARCH REACTOR EFFLUENTS (INCORPORATED INTO ANSI/ ANS 15.11-1987) | |
| ANS 15.16 | EN-Emergency planning for research reactors | |
| ANS 15.2 | EN-Quality Control for Plate-Type Uranium-Aluminum Fuel Elements | |
| ANS 15.2 | EN-QUALITY CONTROL FOR PLATE-TYPE URANIUM-ALUMINUM FUEL ELEMENTS (R 1982) (ANSI N398-1974) | |
| ANS 15.4 | EN-SELECTION AND TRAINING OF PERSONNEL FOR RESEARCH REACTORS | |
| ANS 15.4 | EN-Selection and training of personnel for research reactors | |
| ANS 15.8 | EN-QUALITY ASSURANCE PROGRAM REQUIREMENTS FOR RESEARCH REACTORS (ANSI N402-1976) (R 1995) | |
| ANS 16.1 | EN-Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure | |
| ANS 18.1 | EN-SOURCE TERM SPECIFICTION | |
| ANS 18.1 | EN-Radioactive Source Term for Normal Operation of Light Water Reactors | |
| ANS 19.3 | EN-DETERMINATION OF NEUTRON REACTION RATE DISTRIBUTIONS AND REACTIVITY OF NUCLEAR REACTORS | |
| ANS 19.3.4 | EN-The Determination of Thermal Energy Deposition Rates in Nuclear Reactors | |
| ANS 19.5 | EN-REQUIREMENTS FOR REFERENCE REACTOR PHYSICS MEASUREMENTS (R 1984) | |
| ANS 2.10 | EN-GUIDELINES FOR RETRIEVAL REVIEW PROCESSING AND EVALUATION OF RECORDS OBTAINED FROM SEISMIC INSTRUMENTATION | |
| ANS 2.12 | EN-GUIDELINES FOR COMBINING NATURAL AND EXTERNAL MAN-MADE HAZARDS AT POWER REACTOR SITES | |
| ANS 2.2 | EN-EARTHQUAKE INSTRUMENTATION CRITERIA FOR NUCLEAR POWER PLANTS | |
| ANS 2.23 | EN-Nuclear Plant Response to an Earthquake | |
| ANS 2.3 | EN-STANDARD FOR ESTIMATING TORNADO AND EXTREME WIND CHARACTERISTICS AT NUCLEAR POWER SITES | |
| ANS 2.7 | EN-CRITERIA AND GUIDELINES FOR ASSESSING CAPABILITY FOR SURFACE FAULTING AT NUCLEAR POWER PLANT SITES | |
| ANS 2.8 | EN-DETERMINING DESIGN BASIS FLOODING AT POWER REACTOR SITES | |
| ANS 3.1 | EN-SELECTION QUALIFICATION AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS | |
| ANS 3.1 | EN-SELECTION QUALIFICATION AND TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS | |
| ANS 3.2 | EN-Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants | |
| ANS 3.2 | EN-ADMINISTRATIVE CONTROLS AND QUALITY ASSURANCE FOR THE OPERATIONAL PHASE OF NUCLEAR POWER PLANTS | |
| ANS 3.2 | EN-ADMINISTRATIVE CONTROLS AND QUALITY ASSURANCE FOR THE OPERATIONAL PHASE OF NUCLEAR POWER PLANTS | |
| ANS 3.2 | EN-American National Standard Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants | |
| ANS 3.3 | EN-SECURITY FOR NUCLEAR POWER PLANTS | |
| ANS 3.3 | EN-SECURITY FOR NUCLEAR POWER PLANTS | |
| ANS 3.4 | EN-MEDICAL CERTIFICATION AND MONITORING OF PERSONNEL REQUIRING OPERATOR LICENSES FOR NUCLEAR POWER PLANTS (R 1988) | |
| ANS 3.5 | EN-NUCLEAR POWER PLANT SIMULATORS FOR USE IN OPERATOR TRAINING | |
| ANS 3.5 | EN-Nuclear Power Plant Simulators for Use in Operator Training and Examination | |
| ANS 3.7.1 | EN-FACILITIES AND MEDICAL CARE FOR ON-SITE NUCLEAR POWER PLANT RADIOLOGICAL EMERGENCIES (R 1986) | |
| ANS 3.7.2 | EN-EMERGENCY CONTROL CENTERS FOR NUCLEAR POWER PLANTS (WITHDRAWN) | |
| ANS 3.7.3 | EN-RADIOLOGICAL EMERGENCY PREPAREDNESS EXERCISES FOR NUCLEAR POWER PLANTS (WITHDRAWN) | |
| ANS 3.8.1 | EN-CRITERIA FOR EMERGENCY RESPONSE FUNCTIONS AND ORGANIZATIONS | |
| ANS 3.8.2 | EN-CRITERIA FOR FUNCTIONAL AND PHYSICAL CHARACTERISTICS OF EMERGENCY RESPONSE FACILITIES | |
| ANS 3.8.3 | EN-CRITERIA FOR EMERGENCY RESPONSE PLANS AND IMPLEMENTING PROCEDURES | |
| ANS 40.35 | EN-VOLUME REDUCTION OF LOW LEVEL RADIOACTIVE WASTE | |
| ANS 40.37 | EN-Mobile Radioactive Waste Processing Systems | |
| ANS 5.1 | EN-DECAY HEAT POWER IN LIGHT WATER REACTORS (R 1985) | |
| ANS 5.4 | EN-METHOD FOR CALCULATING THE FRACTIONAL RELEASE OF VOLATILE FISSION PRODUCTS FROM OXIDE FUEL | |
| ANS 51.10 | EN-AUXILIARY FEEDWATER SYSTEM FOR PRESSURIZED WATER REACTORS | |
| ANS 51.10 | EN-Auxiliary Feedwater System for Pressurized Water Reactors | |
| ANS 51.7 | EN-SINGLE FAILURE CRITERIA FOR PWR FLUID SYSTEMS (ANSI N658-1976) | |
| ANS 55.1 | EN-SOLID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER COOLED REACTOR PLANTS-DOCUMENT NOT AVAILABLE | |
| ANS 55.1 | EN-Solid Radioactive Waste Processing System for Light-Water-Cooled Reactor Plants | |
| ANS 55.4 | EN-GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS | |
| ANS 55.4 | EN-Gaseous Radioactive Waste Processing Systems for Light Water Reactor Plants | |
| ANS 55.6 | EN-LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS | |
| ANS 55.6 | EN-Liquid Radioactive Waste Processing System for Light Water Reactor Plants | |
| ANS 56.2 | EN-CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS (ANSI N271-1976) | |
| ANS 56.6 | EN-PRESSURIZED WATER REACTOR CONTAINMENT VENTILATION SYSTEMS | |
| ANS 56.8 | EN-CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS | |
| ANS 56.8 | EN-CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS | |
| ANS 57.1 | EN-DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR FUEL HANDLING SYSTEMS | |
| ANS 57.2 | EN-DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES AT NUCLEAR POWER PLANTS | |
| ANS 57.3 | EN-DESIGN REQUIREMENTS FOR NEW FUEL STORAGE FACILITIES AT LIGHT WATER REACTOR PLANTS | |
| ANS 57.5 | EN-LIGHT WATER REACTORS FUEL ASSEMBLY MECHANICAL DESIGN AND EVALUATION | |
| ANS 57.7 | EN-DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (WATER POOL TYPE) | |
| ANS 57.8 | EN-FUEL ASSEMBLY IDENTIFICATION (R 1987) | |
| ANS 57.9 | EN-DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (DRY STORAGE TYPE) | |
| ANS 58.11 | EN-COOLDOWN CRITERIA FOR LIGHT WATER REACTORS (R 1989) | |
| ANS 58.2 | EN-DESIGN BASIS FOR PROTECTION OF LIGHT WATER NUCLEAR POWER PLANTS AGAINST EFFECTS OF POSTULATED PIPE RUPTURE | |
| ANS 58.21 | EN-External-Events PRA Methodology |
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