ANS Collection
This collection contains documents from the following standards organization(s): American Nuclear Society
| ANS 10.2 | EN-Portability of Scientific and Engineering Software | |
| ANS 10.4 | EN-verification and validation of non-safety-related scientific and engineering computer programs for the nuclear industry | |
| ANS 10.5 | EN-accommodating user needs in scientific and engineering computer software development | |
| ANS 14.1 | EN-Operation of Fast Pulse Reactors | |
| ANS 15.1 | EN-The development of technical specifications for research reactors | |
| ANS 15.11 | EN-radiation protection at research reactor facilities | |
| ANS 15.16 | EN-Emergency planning for research reactors | |
| ANS 15.17 | EN-Fire protection program cCriteria for research reactors | |
| ANS 15.2 | EN-Quality Control for Plate-Type Uranium-Aluminum Fuel Elements | |
| ANS 15.21 | EN-Format and Content for Safety Analysis Reports 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 | |
| ANS 16.1 | EN-Measurement of the leachability of solidified low-level radioactive wastes by a short-term test procedure | |
| ANS 19.1 | EN-Nuclear Data Sets for Reactor Design Calculations | |
| ANS 19.10 | EN-Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals | |
| ANS 19.11 | EN-Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors | |
| ANS 19.3 | EN-Determination of Steady-State Neutron Reaction-Rate Distributions and Reactivity of Nuclear Power Reactors | |
| ANS 19.3.4 | EN-The Determination of Thermal Energy Deposition Rates in Nuclear Reactors | |
| ANS 19.4 | EN-A guide for acquisition and documentation of reference power reactor physics measurements for nuclear analysis verification | |
| ANS 19.6.1 | EN-Reload Startup Physics Tests for Pressurized Water Reactors | |
| ANS 2.10 | EN-Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation | |
| ANS 2.2 | EN-Earthquake Instrumentation Criteria for Nuclear Power Plants | |
| ANS 2.23 | EN-Nuclear Plant Response to an Earthquake | |
| ANS 2.26 | EN-Categorization of nuclear facility structures systems and components for seismic design | |
| ANS 2.27 | EN-criteria for investigations of nuclear facility sites for seismic hazard assessments | |
| ANS 2.29 | EN-Probabilistic Seismic Hazards Analysis | |
| ANS 3.11 | EN-Determining Meteorological Information at Nuclear Facilities | |
| ANS 3.2 | EN-American National Standard Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants | |
| ANS 3.4 | EN-Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants | |
| ANS 3.5 | EN-Nuclear Power Plant Simulators for Use in Operator Training and Examination | |
| ANS 40.37 | EN-Mobile low-level radioactive waste processing systems | |
| ANS 5.1 | EN-Decay Heat Power in Light Water Reactors | |
| ANS 5.10 | EN-Airborne Release Fractions at Non-Reactor Nuclear Facilities | |
| ANS 51.10 | EN-Auxiliary feedwater system for pressurized water reactors | |
| 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 55.6 | EN-Liquid Radioactive Waste Processing System for Light Water Reactor Plants | |
| ANS 56.8 | EN-Containment System Leakage Testing Requirements | |
| ANS 57.1 | EN-Design Requirements for Light Water Reactor Fuel Handling Systems | |
| ANS 57.10 | EN-Design Criteria for Consolidation of LWR Spent Fuel | |
| ANS 57.5 | EN-Light Water Reactors Fuel Assembly Mechanical Design and Evaluation | |
| ANS 57.8 | EN-Fuel Assembly Identification | |
| ANS 57.9 | EN-Design Criteria for an Independent Spent Fuel Storage Installation (Dry Type) | |
| ANS 58.11 | EN-Design criteria for safe shutdown following selected design basis events in light water reactors-Addendum:07/23/2002 | |
| ANS 58.21 | EN-External-Events PRA Methodology | |
| ANS 58.23 | EN-fire PRA methodology | |
| ANS 58.3 | EN-Physical Protection for Nuclear Safety-Related Systems and Components | |
| ANS 58.6 | EN-Criteria for Remote Shutdown for Light Water Reactors | |
| ANS 58.8 | EN-Time Response Design Criteria for Safety-Related Operator Actions | |
| ANS 58.9 | EN-Single failure criteria for light water reactor safety-related fluid systems | |
| ANS 59.3 | EN-Nuclear Safety Criteria for Control Air Systems | |
| ANS 59.51 | EN-Fuel Oil Systems for Safety-Related Emergency Diesel Generators | |
| ANS 59.52 | EN-Lubricating Oil Systems for Safety-Related Emergency Diesel Generators | |
| ANS 6.1.2 | EN-Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants | |
| ANS 6.1.2 | EN-Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants | |
| ANS 6.3.1 | EN-Program for Testing Radiation Shields in Light Water Reactors (LWR) | |
| ANS 6.4 | EN-Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants | |
| ANS 6.4 | EN-Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants | |
| ANS 6.4.2 | EN-Specification for Radiation Shielding Materials | |
| ANS 6.6.1 | EN-Calculation and measurement of direct and scattered gamma radiation from LWR nuclear power plants | |
| ANS 8.1 | EN-Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors | |
| ANS 8.1 ERTA | ||
| ANS 8.10 | EN-Criteria for nuclear criticality safety controls in operations with shielding and confinement | |
| ANS 8.12 | EN-Nuclear criticality control and safety of plutonium-uranium fuel mixtures outside reactors | |
| ANS 8.14 | EN-use of soluble neutron absorbers in nuclear facilities outside reactors | |
| ANS 8.15 | EN-Nuclear criticality control of special actinide elements | |
| ANS 8.17 | EN-Criticality Safety Criteria for the Handling Storage and Transportation of LWR Fuel Outside Reactors | |
| ANS 8.19 | EN-Administrative Practices for Nuclear Criticality Safety | |
| ANS 8.20 | EN-Nuclear criticality safety training | |
| ANS 8.21 | EN-Use of fixed neutron absorbers in nuclear facilities outside reactors | |
| ANS 8.22 | EN-Nuclear Criticality Safety Based on Limiting and Controlling Moderators | |
| ANS 8.23 | EN-Nuclear Criticality Accident Emergency Planning and Response | |
| ANS 8.24 | EN-validation of neutron transport methods for nuclear criticality safety calculations | |
| ANS 8.26 | EN-Criticality safety engineer training and qualification program | |
| ANS 8.27 | EN-Burnup Credit for LWR Fuel | |
| ANS 8.3 | EN-Criticality accident alarm system | |
| ANS 8.5 | EN-Use of borosilicate-glass Raschig rings as a neutron absorber in solutions of fissile material | |
| ANS 8.6 | EN-Safety in conducting subcritical neutron-multiplication measurements in situ | |
| ANS 8.7 | EN-Nuclear Criticality Safety in the Storage of Fissile Materials |