BS ISO 14152:2001

Foreword
Introduction
1 Scope
2 Normative references
3 Terms and definitions
4 Basic rules and principles for the definition
   of neutron shielding
5 Choice of radiological objectives and other
   design criteria
6 Characterization of neutron sources
7 Identification of constraints on placement
   and construction
8 Choice of materials
9 Choice of the calculation method
10 Choice of the final solution
11 Experimental verification
Annex A (informative) Considerations on neutron
        sources
Annex B (informative) Neutron sources and threshold
        reactions
Annex C (informative) Characteristics of the most
        common neutron shielding materials
Annex D (informative) Available computer codes
        for determination of neutron radiation
        protection shielding
Annex E (informative) Simplified shielding calculation
        method for neutrons produced by D-T reactions
Annex F (informative) Simplified neutron shielding
        calculation method
Bibliography

Gives the general methodology governing the design of neutron radiation protection shielding and the choice of neutron radiation protection shielding materials.

This International Standard presents the general methodology governing the design of neutron radiation protection shielding and the choice of neutron radiation protection shielding materials.

This International Standard is applica ble to facilities and operations where neutron sources are located and used, and where workers are occupationally exposed. These operations and facilities vary considerably in design and purpose. These facilities and operations include, but are not limited to:

• nuclear power plants;

• research reactors;

• particle accelerators and neutron generators;

• fusion research facilities;

• transportation packaging for radioactive materials operations;

• medical treatment and research facilities and applications;

• industrial applications such as use of devices for measuring and detecting moisture and density level;

• space applications;

• calibration facilities;

• radiographic installations;

• nuclear fuel cycle installations (reprocessing plants, plutonium solution handling facilities, shielded cells, waste storage, etc.).

The criteria for the design of neutron shielding and the choice of shielding materials contained in this International Standard should be applied to the design of neutron radiation protection shielding systems in such facilities.