ASTM International - ASTM C1187-07
Standard Guide for Establishing Surveillance Test Program for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
|Publication Date:||1 July 2007|
|ICS Code (Radiation protection):||13.280|
|ICS Code (Fissile materials and nuclear fuel technology):||27.120.30|
significance And Use:
The storage of nuclear fuel in high-density storage racks is dependent upon the presence and performance of an absorber between the stored fuel assemblies to ensure that the reactivity of the... View More
The storage of nuclear fuel in high-density storage racks is dependent upon the presence and performance of an absorber between the stored fuel assemblies to ensure that the reactivity of the storage configuration does not exceed the K-effective allowed by applicable regulations. A confirmation test may be required to verify the presence and performance of the absorber within the racks. When the absorbers are not visible or accessible for inspection (such as being fixed within the walls of the structure surrounding the storage position in the rack) a surveillance test program may be conducted on representative specimens of the absorber that are accessible and exposed to the same environmental factors as those in the rack.
This guide provides guidance for establishing and conducting a surveillance program for monitoring the ongoing performance of the absorbers.View Less
1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear spent fuel storage racks in a pool environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program to verify the presence of sufficient neutron absorbing material within the storage racks. The performance of a surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear spent fuel.
1.2 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.