Popular Standards |
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ANS 1 | CONDUCT OF CRITICAL EXPERIMENT |
ANS 10.2 | PORTABILITY OF SCIENTIFIC AND ENGINEERING SOFTWARE |
ANS 10.3 | DOCUMENTATION OF COMPUTER SOFTWARE |
ANS 10.4 | GUIDELINES FOR THE VERIFICATION AND VALIDATION OF SCIENTIFIC AND ENGINEERING COMPUTER PROGRAMS FOR THE NUCLEAR INDUSTRY |
ANS 10.5 | ACCOMMODATING USER NEEDS IN SCIENTIFIC AND ENGINEERING COMPUTER SOFTWARE DEVELOPMENT |
ANS 11.13 | CONCRETE RADIATION SHIELDS |
ANS 14.1 | OPERATION OF FAST PULSE REACTORS |
ANS 15.1 | THE DEVELOPMENT OF TECHNICAL SPECIFICATIONS FOR RESEARCH REACTORS |
ANS 15.10 | DECOMMISSIONING OF RESEARCH REACTORS |
ANS 15.11 | RADIATION PROTECTION AT RESEARCH REACTOR FACILITIES |
ANS 15.12 | DESIGN OBJECTIVES, MONITORING OF SYSTEMS CONTROL- |
ANS 15.15 | CRITERIA FOR THE REACTOR SAFETY SYSTEMS OF RESEARCH |
ANS 15.16 | EMERGENCY PLANNING FOR RESEARCH REACTORS |
ANS 15.17 | FIRE PROTECTION PROGRAM CRITERIA FOR RESEARCH REACTORS |
ANS 15.19 | SHIPMENT AND RECEIPT OF SPECIAL NUCLEAR MATERIAL (SNM) BY RESEARCHREACTOR FACILITIES |
ANS 15.2 | QUALITY CONTROL FOR PLATE-TYPE URANIUM ALUMINUM FUEL ELEMENTS |
ANS 15.21 | FORMAT AND CONTENT FOR SAFETY ANALYSIS REPORTS FOR RESEARCH REACTORS |
ANS 15.4 | SELECTION AND TRAINING OF PERSONNEL FOR RESEARCH REACTORS |
ANS 15.6 | REVIEW OF EXPERIMENTS FOR RESEARCH REACTORS |
ANS 15.7 | REASEARCH REACTOR SITE EVALUATION |
ANS 15.8 | QUALITY ASSURANCE PROGRAM REQUIREMENTS FOR RESEARCH REACTORS |
ANS 16.1 | MEASUREMENT OF THE LEACHABILITY OF SOLIDIFIED LOW-LEVEL RADIOACTIVE WASTES BY A SHORT-TERM TEST PROCEDURE |
ANS 1690010 | GLOSSARY OF TERMS IN NUCLEAR SCIENCE & TECHNOLOGY |
ANS 18.1 | RADIOACTIVE SOURCE TERM FOR NORMAL OPERATION OF LIGHT WATER REACTORS |
ANS 18.5 | SURVEYS OF TERRESTRIAL ECOLOGY NEEDED TO LICENSE THERMAL POWER PLANTS |
ANS 19.1 | NUCLEAR DATA SETS FOR REACTOR DESIGN CALCULATIONS |
ANS 19.11 | CALCULATION AND MEASUREMENT OF THE MODERATOR TEMPERTURE COEFFICIENT OF REACTIVITY FOR WATER MODERATED POWER REACTORS |
ANS 19.3 | DETERMINATION OF STEADY-STATE NEUTRON REACTION-RATE DISTRIBUTIONS AND REACTIVITY OF NUCLEAR POWER REACTORS |
ANS 19.3.4 | THE DETERMINATION OF THERMAL ENERGY DEPOSITION RATES IN NUCLEAR REACTORS |
ANS 19.4 | A GUIDE FOR ACQUISITION AND DOCUMENTATION OF REFERENCE POWER REACTOR PHYSICS MEASUREMENTS FOR NUCLEAR ANALYSIS VERIFICATION |
ANS 19.5 | REQUIREMENTS FOR REFERENCE REACTOR PHYSICS MEASUREMENTS |
ANS 19.6.1 | RELOAD STARTUP PHYSICS TESTS FOR PRESSURIZED WATER REACTORS |
ANS 2.10 | CRITERIA FOR THE HANDLING AND INITIAL EVALUATION OF RECORDS FROM NUCLEAR POWER PLANT SEISMIC INSTRUMENTATION |
ANS 2.11 | GUIDELINES FOR EVALUATING SITE-RELATED GEOTECHNICA |
ANS 2.12 | GUIDELINES FOR COMBINING NATURAL AND EXTERNAL MAN- |
ANS 2.13 | EVALUATION OF SURFACE-WATER SUPPLIES FOR NUCLEAR |
ANS 2.17 | EVALUATION OF RADIOMUCLIDE TRANSPORT IN GROUND WAT |
ANS 2.19 | GUIDELINES FOR ESTABLISHING SITE RELATED PARAMETER |
ANS 2.2 | EARTHQUAKE INSTRUMENTATION CRITERIA FOR NUCLEAR POWER PLANTS |
ANS 2.23 | NUCLEAR PLANT RESPONSE TO AN EARTHQUAKE |
ANS 2.26 | CATEGORIZATION OF NUCLEAR FACILITY STRUCTURES, SYSTEMS AND COMPONENTS FOR SEISMIC DESIGN |
ANS 2.3 | ESTIMATING TORNADO & EXTREME WIND CHARACTERISTICS AT NUCLEAR POWER PLANTS |
ANS 2.5 | STANDARD FOR DETERMINING METOROLOGICAL INFORMATION |
ANS 2.7 | CRITERIA AND GUIDELINES FOR ASSESSING CAPABILITY |
ANS 2.8 | DETERMINING DESIGN BASIS FLOODING AT POWER REACTOR |
ANS 2.9 | EVALUATION OF GROUND WATER SUPPLY FOR NUCLEAR POWE |
ANS 3.1 | SELECTION, QUALIFICATION & TRAINING OF PERSONNEL FOR NUCLEAR POWER PLANTS |
ANS 3.11 | DETERMINING METEOROLOGICAL INFORMATION AT NUCLEAR FACILITIES |
ANS 3.2 | ADMINISTRATIVE CONTROLS & QUALITY ASSURANCE FOR THE OPERATIONAL PHASE OF NUCLEAR POWER PLANTS |
ANS 3.3 | SECURITY FOR NUCLEAR POWER PLANTS |
ANS 3.4 | MEDICAL CERTIFICATION AND MONITORING OF PERSONNEL REQUIRING OPERATOR LICENSES FOR NUCLEAR POWER PLANTS |
ANS 3.5 | NUCLEAR POWER PLANT SIMULATORS FOR USE IN OPERATOR TRAINING AND EXAMINATION |
ANS 3.7.1 | FACILITIES AND MEDICAL CARE FOR ONSITE NUCLEAR POWER PLANT RADIOLOGICAL EMERGENCIES |
ANS 3.7.2 | EMERGENCY CONTROL CENTERS FOR NUCLEAR POWER PLANTS |
ANS 3.7.3 | RADIOLOGICAL EMERGENCY PREPAREDNESS EXERCISES FOR |
ANS 3.8.1 | CRITERIA FOR RADIOLOGICAL EMERGENCY RESPONCE FUNCTIONS AND ORGANIZATION |
ANS 3.8.2 | CRITERIA FOR FUNCTIONAL AND PHYSICAL CHARACTERISTICS OF EMERGENCY RESPONSE FACILITIES |
ANS 3.8.3 | CRITERIA FOR EMERGENCY RESPONSE PLANS AND IMPLEMENTING PROCEDURES |
ANS 3.8.4 | CRITERIA FOR MAINTAINING RADIOLOGICAL EMERGENCY RESPONSE CAPABILITY |
ANS 3.8.5 | CRITERIA FOR EMERGENCY RADIOLOGICAL FIELD MONITORING SAMPLING AND ANALYSIS |
ANS 3.8.6 | CRITERIA FOR THE CONDUCT OF OFF - SIGHT RADIOLOGICAL ASSESSMENT FOR EMERGENCY RESPONSE FOR NUCLEAR POWER PLANTS |
ANS 3.8.7 | CRITERIA FOR PLANNING, DEVELOPMENT, CONDUCT, AND EVALUATION OF DRILLS AND EXERCISES FOR EMERGENCY PREPAREDNESS |
ANS 4.1 | DESIGN BASIS CRITERIA FOR SAFETY SYS.NUCLEAR STATN |
ANS 4.5 | CRITERIA FOR ACCIDENT MONITORING FUNCTIONS IN LIGH |
ANS 40.35 | VOLUME REDUCTION OF LOW LEVEL RADIOACTIVE WASTE |
ANS 40.37 | MOBILE RADIOACTIVE WASTE PROCESSING SYSTEMS |
ANS 5.1 | DECAY HEAT POWER IN LIGHT WATER REACTORS |
ANS 5.10 | AIRBORNE RELEASE FRACTIONS AT NON-REACTOR NUCLEAR FACILITIES |
ANS 5.4 | METHOD FOR CALCULATING THE RELEASE OF FISSION PROD |
ANS 51.1 | NUCLEAR SAFETY CRITERIA FOR DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
ANS 51.10 | AUXILIARY FEEDWATER SYSTEM FOR PRESSURIZED WATER REACTOR |
ANS 52.1 | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATERREACTOR PLANTS |
ANS 54.1 | GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT |
ANS 54.2 | DESIGN BASIS FOR FACILITIES FOR LMFBR SPENT FUEL- |
ANS 54.8 | LIQUID METAL FIRE PROTECTION IN LMR PLANTS |
ANS 55.1 | SOLID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT-WATER-COOLED REACTOR PLANTS |
ANS 55.4 | GASEOUS RADIOACTIVE WASTE PROCESSING SYSTEMS FOR LIGHT WATER REACTOR PLANTS |
ANS 55.6 | LIQUID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT WATER REACTOR PLANTS |
ANS 56.10 | SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT AYALYSIS IN LIGHT WATER REACTORS |
ANS 56.11 | DESIGN CRITERIA FOR PROTECTION AGAINST THE EFFECTS OF COMPARTMENT FLOODING IN LIGHT WATER REACTOR PLANTS |
ANS 56.2 | CONTAINMENT ISOLATION PROVISIONS FOR LIQUID SYSTEM |
ANS 56.27 | CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS |
ANS 56.3 | OVERPRESSURE PROTECTION OF LOW PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
ANS 56.4 | PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS |
ANS 56.5 | PWR & BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA |
ANS 56.6 | PRESSURIZED WATER REACTOR CONTAINMENT VENTILATION |
ANS 56.7 | BOILING WATER REACTOR CONTAINMENT VENTILATION SYST |
ANS 56.8 | CONTAINMENT SYSTEM LEAKAGE TESTING REQUIREMENTS |
ANS 57.1 | DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR FUEL HANDLING SYSTEMS |
ANS 57.10 | DESIGN CRITERIA FOR CONSOLIDATION OF LWR SPENT FUEL |
ANS 57.2 | DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR SPENT |
ANS 57.3 | DESIGN REQUIREMENTS FOR NEW FUEL STORAGE FACILITIE |
ANS 57.5 | LIGHT WATER REACTORS FUEL ASSEMBLY MECHANICAL DESIGN |
ANS 57.7 | DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION(WATER POOL TYPE) |
ANS 57.8 | FUEL ASSEMBLY IDENTIFICATION |
ANS 57.9 | DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION(DRY TYPE) |
ANS 58.11 | DESIGN CRITERIA FOR SAFE SHUTDOWN FOLLOWING SELECTED DESIGN BASIS EVENTS IN LIGHT WATER REACTORS |
ANS 58.14 | SAFETY AND PRESSURE INTEGRITY CLASSIFICATION CRITERIA FOR LIGHT WATER REACTORS |
ANS 58.2 | DESIGN BASIS FOR PROTECTION OF LIGHT WATER NUCLEAR POWER PLANTS AGAINST THE EFFECTS OF POSTULATED PIPE RUPTURE |
ANS 58.21 | EXTERNAL-EVENTS PRA METHODOLOGY |
ANS 58.23 | FIRE PRA METHODOLOGY |
ANS 58.3 | PHYSICAL PROTECTION FOR NUCLEAR SAFETY-RELATED SYSTEMS AND COMPONENTS |
ANS 58.4 | CRITERIA FOR TECHNICAL SPECIFICATIONS FOR NUCLEAR |
ANS 58.6 | CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTOR |
ANS 58.8 | TIME RESPONSE DESIGN CRITERIA FOR SAFETY-RELATED OPERATOR ACTIONS |
ANS 58.9 | SINGLE FAILURE CRITERIA FOR LIGHT WATER REACTOR SAFETY-RELATED FLUID SYSTEMS |
ANS 59.1 | NUCLEAR SAFETY RELATED COOLING WATER SYSTEM |
ANS 59.2 | SAFETY CRITERIA FOR HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT |
ANS 59.3 | NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS |
ANS 59.4 | GENERIC REQUIREMENTS FOR LIGHT WATER NUCLEAR POWER |
ANS 59.51 | FUEL OIL SYSTEM FOR EMERGENCY DIESEL GENERATORS |
ANS 59.52 | LUBRICATING OIL SYSTEMS FOR SAFETY RELATED EMERGENCY DIESEL GENERATORS |
ANS 6.1.1 | NEUTRON & GAMMA-RAY FLUX-TO-DOSE-RATE FACTORS |
ANS 6.1.2 | NEUTRON AND GAMMA-RAY CROSS SECTIONS FOR NUCLEAR RADIATION PROTECTION CALCULATIONS FOR NUCLEAR POWER PLANTS |
ANS 6.3.1 | PROGRAM FOR TESTING RADIATION SHIELDS IN LIGHT WAT |
ANS 6.4 | NUCLEAR ANALYSIS AND DESIGN OF CONCRETE RADIATION SHIELDING FOR NUCLEAR POWER PLANTS |
ANS 6.4.2 | SPECIFICATION FOR RADIATION SHIELDING MATERIALS |
ANS 6.4.3 | GAMMA-RAY ATTENUATION COEFFICIENTS AND BUILDUP FACTORS FOR ENGINEERING MATERIALS |
ANS 6.6.1 | CALCULATION AND MEASUREMENT OF DIRECT AND SCATTERED GAMMA RADIATION FROM LWR NUCLEAR POWER PLANTS |
ANS 6.8.1 | LOCATION AND DESIGN CRITERIA FOR AREA RADIATION |
ANS 7.4.3.2 | PROGRAMMABLE DIGITAL COMPUTER SYSTEMS |
ANS 8.1 | NUCLEAR CRITICALITY SAFETY IN OPERATIONS WITH FISSIONABLE MATERIALS OUTSIDE REACTORS |
ANS 8.10 | CRITERIA FOR NUCLEAR CRITICALITY SAFETY CONTROLS IN OPERATIONS WITH SHIELDING AND CONFINEMENT |
ANS 8.11 | VALIDATION,CALCULATION METHODS, NUCLEAR SAFETY |
ANS 8.12 | NUCLEAR CRITICALITY CONTROL AND SAFETY OF PLUTONIUM-URANIUM FUEL MIXTURE OUTSIDE REACTORS |
ANS 8.14 | USE OF SOLUBLE NEUTRON ABSORBERS IN NUCLEAR FACILITIES OUTSIDE REACTORS |
ANS 8.15 | NUCLEAR CRITICALITY CONTROL OF SPECIAL ACTINIDE ELEMENTS |
ANS 8.17 | CRITICALITY SAFETY CRITERIA FOR THE HANDLING, STORAGE AND TRANSPORTATION OF LWR FUEL OUTSIDE REACTORS |
ANS 8.19 | ADMINISTRATIVE PRACTICES FOR NUCLEAR CRITICALITY SAFETY |
ANS 8.20 | NUCLEAR CRITICALITY SAFETY TRAINING |
ANS 8.21 | USE OF FIXED NEUTRON ABSORBERS IN NUCLEAR FACILITIES OUTSIDE REACTORS |
ANS 8.22 | NUCLEAR CRITICALITY SAFETY BASED ON LIMITING AND CONTROLLING MODERATORS |
ANS 8.23 | NUCLEAR CRITICALITY ACCIDENT EMERGENCY PLANNING AND RESPONSE |
ANS 8.24 | VALIDATION OF NEUTRON TRANSPORT METHODS FOR NUCLEAR CRITICALITY SAFETY CALCULATIONS |
ANS 8.26 | CRITICALITY SAFETY ENGINEER TRAINING AND QUALIFICATION PROGRAM |
ANS 8.3 | CRITICALITY ACCIDENT ALARM SYSTEM |
ANS 8.5 | USE OF BOROSILICATE-GLASS RASCHIG RINGS AS A NEUTRON ABSORBER IN SOLUTIONS OF FISSILE MATERIAL |
ANS 8.6 | SAFETY IN CONDUCTING SUBCRITICAL NEUTRON-MULTIPLICATION MEASUREMENTS IN SITU |
ANS 8.7 | GUIDE FOR NUCLEAR CRITICALITY IN THE SAFETY OF STORAGE OF FISSILE MATERIALS |
ANS 8.9 | NUCLEAR CRITICALITY SAFETY GUIDE FOR STEEL-PIPE INTERSECTIONS INTERSECTIONS CONTAINING AQUEOUS SOLUTIONS OF FISSILE MATERIALS |
ANS 9 | GLOSSARY OF TERMS IN NUCLEAR SCIENCE & TECHNOLOGY |
ANS BOOK 1 | NUCLEAR POWER AND THE ENVIRONMENT - Q & A RADIATION |
ANS GLOSSARY OF TERMS | GLOSSARY OF TERMS IN NUCLEAR SCIENCE AND TECHNOLOGY #690010 |
ANS INDEX | AMERICAN NUCLEAR SOCIETY PUBLICATIONS CATALOG |
ANS N2.3 | IMMEDIATE EVACUATION SIGNAL FOR USE IN INDUSTRIAL |
ANS STANDARDS | COMPILATION OF ANS STANDARDS-1974 AND 1977 COMPLETE TEXT |
ANS STANDARDS V1 | COMPILATION OF ANS STANDARDS - VOLUME 1 |
ANS STANDARDS V2 | COMPILATION OF ANS STANDARDS - VOLUME 2 |
ANSI N101.6 | CONCRETE RADIATION SHIELDS |
ANSI N18.17 | SECURITY FOR NUCLEAR POWER PLANTS |
ANSI N18.5 | EARTHQUAKE INSTRUMENTATION CRITERIA/NUCLEAR POWER- |
ANSI N652 | A GUIDE FOR ACQUISITION AND DOCUMENTATION OF REFERENCE POWER REACTOR PHYSICS MEASUREMENTS FOR NUCLEAR ANALYSIS VERIFICATION |
