ASTM C1187-91(1999)
(Guide)Standard Guide for Establishing Surveillance Test Program for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
Standard Guide for Establishing Surveillance Test Program for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
SCOPE
1.1 This guide provides advice for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) in nuclear spent fuel storage racks. The recommended 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.
General Information
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Standards Content (Sample)
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn. Contact ASTM
International (www.astm.org) for the latest information.
Designation:C1187–91 (Reapproved 1999)
Standard Guide for
Establishing Surveillance Test Program for Boron-Based
Neutron Absorbing Material Systems for Use in Nuclear
Spent Fuel Storage Racks
This standard is issued under the fixed designation C 1187; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
1. Scope D 2240 Test Method for Rubber Property—Durometer
Hardness
1.1 This guide provides advice for establishing a surveil-
D 3183 Practice for Rubber—Preparation of Pieces for Test
lance test program to monitor the performance of boron-based
Purposes from Products
neutron absorbing material systems (absorbers) in nuclear
D 4483 Practice for Determining Precision for Test Method
spent fuel storage racks.The recommended practices presented
Standards in the Rubber and Carbon Black Industries
inthisguide,whenimplemented,willprovideacomprehensive
E6 Terminology Relating to Methods of Mechanical Test-
surveillance test program to verify the presence of sufficient
ing
neutron absorbing material within the storage racks. The
E8 Test Methods forTensionTesting of Metallic Materials
performance of a surveillance test program provides added
E 23 Test Methods for Notched Bar Impact Testing of
assurance of the safe and effective operation of a high-density
Metallic Materials
storage facility for nuclear spent fuel.
E74 Practice for Calibration of Force Measuring Instru-
1.2 This standard does not purport to address all of the
ments for Verifying the Force Indication of Testing Ma-
safety problems, if any, associated with its use. It is the
chines
responsibility of the user of this standard to establish appro-
E 290 TestMethodforSemi-GuidedBendTestforDuctility
priate safety and health practices and determine the applica-
of Metallic Materials
bility of regulatory limitations prior to use.
E 1027 Practice for Exposure of Polymeric Materials to
2. Referenced Documents Ionizing Radiation
G1 Practice for Preparing, Cleaning, and Evaluating Cor-
2.1 ASTM Standards:
rosion Test Specimens
C 859 Terminology Relating to Nuclear Materials
G4 Method for Conducting Corrosion Coupon Tests in
C 992 Specification for Boron-Based Neutron Absorbing
Plant Equipment
Material Systems for Use in Nuclear Spent Fuel Storage
G15 Terminology Relating to Corrosion and Corrosion
Racks
Testing
C 1068 Guide for Qualification of Measurement Methods
G16 Guide forApplying Statistics toAnalysis of Corrosion
by a Laboratory Within the Nuclear Industry
Data
D 412 Test Methods for Vulcanized Rubber and Thermo-
G46 Practice for Examination and Evaluation of Pitting
plastic Rubbers and Thermoplastic Elastomers—Tension
Corrosion
D 430 Test Methods for Rubber Deterioration—Dynamic
G69 Practice for Measurement of Corrosion Potentials of
Fatigue
Aluminum Alloys
D 518 Test Method for Rubber Deterioration—Surface
Cracking
3. Terminology
D 813 Test Method for Rubber Deterioration—Crack
3.1 Definitions of Terms Specific to This Standard:
Growth
Terms shall be defined in accordance with Terminology
D 1415 Test Method for Rubber Property—International
C 859 except as defined as follows:
Hardness
3.1.1.1 absorber—a boron-based neutron-absorbing mate-
rial system.
This guide is under the jurisdiction ofASTM Committee C-26 on Nuclear Fuel
Cycle and is the direct responsibility of Subcommittee C26.03 on NeutronAbsorber
Materials Specifications.
Current edition approved May 15, 1991. Published July 1991. Annual Book of ASTM Standards, Vol 03.01.
2 5
Annual Book of ASTM Standards, Vol 12.01. Annual Book of ASTM Standards, Vol 12.02
3 6
Annual Book of ASTM Standards, Vol 09.01. Annual Book of ASTM Standards, Vol 03.02.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn. Contact ASTM
International (www.astm.org) for the latest information.
C1187–91 (1999)
3.1.1.2 high-density storage—the close-packing of spent both. The monitoring may also include consideration of radia-
fuel to the extent that absorbers are required for neutron flux tion damage or other types of deterioration that may reduce the
reduction. physical integrity or neutron performance of the absorber
3.1.1.3 irradiation—the neutron, beta and gamma fluxes, belowthepredeterminedlimitsforthedesignservicelifeofthe
from spent-fuel assemblies in a water-filled spent fuel pool. racks (see 8.3).
3.1.1.4 neutron attenuation—that fraction of the neutron
6. Surveillance Specimens
flux striking the surface of the absorber that is not transmitted
through it. This is a quantitative characteristic.
6.1 Whereverpossible,thedesignofsurveillancespecimens
3.1.1.5 neutron blackness test—a qualitative test using a
shall be in accordance with the requirements of ASTM test
neutron source for locating any unshielded areas within an
methods for the specific properties of interest to be measured.
absorber.
The size and configuration of certain specimens may be
3.1.1.6 sample—one or more specimens of the absorber
representative of those contained in the racks (see 6.1.2)in
selected by some predetermined sampling process.
every respect possible, and yet be retrievable from the repre-
3.1.1.7 service life—the period of time for which properties sentative exposure areas of the racks at periodic intervals. The
of the absorber are expected to remain in compliance with the
sizeandconfigurationofthespecimensshallbeappropriatefor
contract requirements.
monitoring those characteristics where changes may be antici-
3.1.1.8 specimen—an individual full-size piece of the ab-
pated such as corrosion effects, radiation shrinkage, or degra-
sorber or any portion thereof selected and prepared as neces-
dation of the physical properties. It is recommended that
sary for test purposes.
archive (benchmark) specimens be retained for the duration of
the surveillance program. In all cases, the exposed and nonex-
4. Significance and Use
posed (archive) specimens shall be of the same size and shape.
4.1 The storage of nuclear spent fuel in high-density storage
6.1.1 The specimens for the metal-based absorbers shall be
racks is dependent upon the presence and performance of an
suitable for neutron attenuation testing, neutron blackness
absorber between the stored fuel assemblies to ensure that the
testing, or both, and any other tests as deemed necessary.
reactivity of the storage configuration does not exceed the
6.1.2 The specimens for the polymer-based absorber shall
K-effective allowed by applicable regulations. The Nuclear
be suitable for neutron attenuation testing, neutron blackness
Regulatory Commission has required in certain instances the
testing, or both, and large enough to obtain practical radiation
verification of the presence and performance of the abso
...
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