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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 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.
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.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
C992 Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
C1068 Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
D412 Test Methods for Vulcanized Rubber and Thermoplastic Elastomers--Tension
D430 Test Methods for Rubber Deterioration--Dynamic Fatigue
D518 Test Method for Rubber Deterioration--Surface Cracking
D813 Test Method for Rubber Deterioration--Crack Growth
D1415 Test Method for Rubber Property--International Hardness
D2240 Test Method for Rubber Property--Durometer Hardness
D3183 Practice for Rubber--Preparation of Pieces for Test Purposes from Products
D4483 Practice for Evaluating Precision for Test Method Standards in the Rubber and Carbon Black Manufacturing Industries
E6 Terminology Relating to Methods of Mechanical Testing
E8 Test Methods for Tension Testing of Metallic Materials
E23 Test Methods for Notched Bar Impact Testing of Metallic Materials
E74 Practice of Calibration of Force-Measuring Instruments for Verifying the Force Indication of Testing Machines
E290 Test Methods for Bend Testing of Material for Ductility
G1 Practice for Preparing, Cleaning, and Evaluating Corrosion Test Specimens
G4 Guide for Conducting Corrosion Tests in Field Applications
G15 Terminology Relating to Corrosion and Corrosion Testing
G16 Guide for Applying Statistics to Analysis of Corrosion Data
G46 Guide for Examination and Evaluation of Pitting Corrosion
G69 Test Method for Measurement of Corrosion Potentials of Aluminum Alloys
ICS Number Code 13.280 (Radiation protection); 27.120.30 (Fissile materials and nuclear fuel technology)
UNSPSC Code 15131500(Nuclear fuel)