ANS 1

Conduct of Critical Experiments

ANS 10.2

Portability of Scientific and Engineering Software

ANS 10.4

Guidelines for the Verification and Validation of Scientific and Engineering Computer Programs for the Nuclear Industry

ANS 14.1

Operation of Fast Pulse Reactors

ANS 15.10

Decommissioning of Research Reactors

ANS 15.11

Radiation Protection at Research Reactor Facilities

ANS 15.16

Emergency Planning for Research Reactors

ANS 15.17

Fire Protection Program Criteria for Research Reactors

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 15.8

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 18.1

Radioactive Source Term for Normal Operation of Light Water Reactors

ANS 19.1

Nuclear Data Sets for Reactor Design Calculations

ANS 19.11

Calculation and Measurement of the Moderator Temperature 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

Guide for Acquisition and Documentation of Reference Power Reactor Physics Measurements for Nuclear Analysis Verification

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 2.2

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 3.1

Selection, Qualification, and Training of Personnel for Nuclear Power Plants

ANS 3.11

Determining Meteorological Information at Nuclear Facilities

ANS 3.2

Administrative Controls and Quality Assurance for the Operational Phase of 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 On-Site Nuclear Power Plant Radiological Emergencies

ANS 3.8.1

Criteria for Radiological Emergency Response Functions and Organizations

ANS 3.8.2

Criteria for Functional and Physical Characteristics of Radiological Emergency Response Facilities

ANS 3.8.3

Criteria for Radiological Emergency Response Plans and Implementing Procedures

ANS 3.8.4

Criteria for Maintaining Radiological Emergency Response Capability

ANS 3.8.6

Criteria for the Conduct of Offsite 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 5.10

Airborne Release Fractions at Non-Reactor Nuclear Facilities

ANS 51.10

Auxiliary Feedwater System for Pressurized Water Reactors

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 57.1

Design Requirements for Light Water Reactor Fuel Handling Systems

ANS 57.10

Design Criteria for Consolidation of LWR Spent Fuel

ANS 57.5

Light Water Reactors Fuel Assembly Mechanical Design and Evaluation

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 58.21

External-Events PRA Methodology

ANS 58.3

Physical Protection for Nuclear Safety-Related Systems and Components

ANS 58.6

Criteria for Remote Shutdown for Light Water Reactors

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 59.3

Nuclear Safety Criteria for Control Air Systems

ANS 59.51

Fuel Oil Systems for Safety-Related Emergency Diesel Generators

ANS 59.52

Lubricating Oil Systems for Safety-Related Emergency Diesel Generators

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 Water Reactors (LWR)

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 6.6.1

Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plants

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 8.12

Nuclear Criticality Control and Safety of Plutonium-Uranium Fuel Mixtures 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 8.3

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

Nuclear Criticality Safety in the Storage of Fissile Materials