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DOE-STD-1135-99
This information can be obtained from various textbooks or Criticality Safety Short
Courses. See Appendix A for available training resources.
The individual should be able to:
a. Describe the types of data derived from critical experiments and their use in
criticality safety.
b. Participate in a criticality experiment or subcritical experiment demonstration.
c. Discuss previous criticality accidents and their causal factors.
4.0 Rules, Standards and Guides
Various laws, standards, and guides have been written which direct the performance
of criticality safety across the complex. These are the references used in
development of this Standard. In order to provide consistent understanding of the
policies and rules governing the function of criticality safety, the individual shall
demonstrate familiarity with the following rules, standards, and guides:
ANSI/ANS-8.1, Nuclear Criticality Safety in Operations with Fissionable
Materials Outside Reactors.
ANSI/ANS-8.3, (ANSI N-16.2), Criticality Accident Alarm System
ANSI/ANS-8.5, (ANSI N-16.4), Use of Borosilicate-Glass Raschig Rings as
a Neutron Absorber in Solutions of Fissile Material.
ANSI/ANS-8.6, Safety in Conducting Subcritical Neutron-Multiplication
Measurements In Situ.
ANSI/ANS-8.7, Guide for Nuclear Criticality Safety in the Storage of Fissile
Materials.
ANSI/ANS-8.9, Nuclear Criticality Safety Criteria for Steel-Pipe
Intersections Containing Aqueous Solutions of Fissile Materials.
ANSI/ANS-8.10, Criteria for Nuclear Criticality Safety Controls in
Operations With Shielding and Confinement.
ANSI/ANS-8.12, Nuclear Criticality Control and Safety of Plutonium-
Uranium Fuel Mixtures Outside Reactors.
ANSI/ANS-8.15, Nuclear Criticality Control of Special Actinide Elements.
ANSI/ANS-8.17, Criticality Safety Criteria for the Handling, Storage and
Transportation of LWR Fuel Outside Reactors.
ANSI/ANS-8.19, Administrative Practices for Nuclear Criticality Safety.
ANSI/ANS-8.20, Nuclear Criticality Safety Training.
ANSI/ANS-8.21, Use of Fixed Neutron Absorbers in Nuclear Facilities
Outside Reactors.
ANSI/ANS-8.22, Nuclear Criticality Safety Based on Limiting and
Controlling Moderators.
ANSI/ANS-8.23, Nuclear Criticality Accident Emergency Planning and
Response.
ANSI/ANS-13.3, Dosimetry for Criticality Accidents.
5


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