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ANS 15.21 : 2012

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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FORMAT AND CONTENT FOR SAFETY ANALYSIS REPORTS FOR RESEARCH REACTORS

Superseded date

21-08-2023

Superseded by

ANS 15.21-2012(R2023)

Published date

12-01-2013

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1. Introduction
    1.1 Scope
    1.2 Definitions
    1.3 Application
            1.3.1 Purpose
            1.3.2 Format
            1.3.3 Style
            1.3.4 International System of Units (SI)
            1.3.5 SAR Table of Contents
            1.3.6 SAR Appendices
            1.3.7 Significant Figures
            1.3.8 Abbreviations
            1.3.9 References
            1.3.10 Security
            1.3.11 Procedures
            1.3.12 Organizations
            1.3.13 Specifications
2. Safety Analysis Report Contents
2.1 Chapter 1, Introduction
2.2 Chapter 2, Site Characteristics
2.3 Chapter 3, General Design of Buildings and Structures
2.4 Chapter 4, Reactor
2.5 Chapter 5, Reactor Coolant System and Connected Systems
2.6 Chapter 6, Engineered Safety Features
2.7 Chapter 7, Instrumentation and Controls
2.8 Chapter 8, Electric Power
2.9 Chapter 9, Auxiliary Systems
2.10 Chapter 10,Experimental Facilities and Utilization
2.11 Chapter 11,Operational Radiological Safety
2.12 Chapter 12,Conduct of Operations
2.13 Chapter 13,Accident Analysis
2.14 Chapter 14,Technical Specifications (or Equivalent Document)
2.15 Chapter 15,Quality Assurance Program
2.16 Chapter 16,Decontamination and Decommissioning
3. References
Appendices
Appendix A Table of Contents for a Research Reactor
            Safety Analysis Report
Appendix B Glossary of Definitions Found in Research Reactor
            Standards (ANS-15 Series)
Appendix C Selected Initiating Events for Research
            Reactor Accident Analysis
Appendix D References Related to Research Reactor
            Safety Analysis Reports

Gives the criteria for the format and content for safety analysis reports (SARs) for research reactors.

DocumentType
Standard
PublisherName
American Nuclear Society
Status
Superseded
SupersededBy
Supersedes

ANS 15.7-1977(R1986) SITE EVALUATION, RESEARCH REACTOR
ANS 15.16 : 2015 EMERGENCY PLANNING FOR RESEARCH REACTORS
ANS 15.4 : 2016 SELECTION AND TRAINING OF PERSONNEL FOR RESEARCH REACTORS
ANS 15.10-1994 DECOMMISSIONING OF RESEARCH REACTORS
ANS 15.15-1978(R1986) SAFETY SYSTEMS OF RESEARCH REACTORS, CRITERIA FOR THE REACTOR
ANS 15.11 : 2016 RADIATION PROTECTION AT RESEARCH REACTOR FACILITIES

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