1、Designation: C 1187 07Standard Guide forEstablishing Surveillance Test Program for Boron-BasedNeutron Absorbing Material Systems for Use in NuclearSpent Fuel Storage Racks1This standard is issued under the fixed designation C 1187; the number immediately following the designation indicates the year
2、oforiginal adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) indicates an editorial change since the last revision or reapproval.1. Scope1.1 This guide provides guidance for establishing a surveil-
3、lance test program to monitor the performance of boron-basedneutron absorbing material systems (absorbers) necessary tomaintain sub-criticality in nuclear spent fuel storage racks in apool environment. The practices presented in this guide, whenimplemented, will provide a comprehensive surveillance
4、testprogram to verify the presence of sufficient neutron absorbingmaterial within the storage racks. The performance of asurveillance test program provides added assurance of the safeand effective operation of a high-density storage facility fornuclear spent fuel.1.2 This standard does not purport t
5、o address all of thesafety problems, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2C 992 Sp
6、ecification for Boron-Based Neutron AbsorbingMaterial Systems for Use in Nuclear Spent Fuel StorageRacksC 1068 Guide for Qualification of Measurement Methodsby a Laboratory Within the Nuclear IndustryD 412 Test Methods for Vulcanized Rubber and Thermo-plastic ElastomersTensionD 430 Test Methods for
7、Rubber DeteriorationDynamicFatigueD 518 Test Method for Rubber DeteriorationSurfaceCrackingD 813 Test Method for Rubber DeteriorationCrackGrowthD 1415 Test Method for Rubber PropertyInternationalHardnessD 2240 Test Method for Rubber PropertyDurometerHardnessD 3183 Practice for RubberPreparation of P
8、roduct Piecesfor Test Purposes from ProductsD 4483 Practice for Evaluating Precision for Test MethodStandards in the Rubber and Carbon Black ManufacturingIndustriesE6 Terminology Relating to Methods of Mechanical Test-ingE8 Test Methods for Tension Testing of Metallic MaterialsE 23 Test Methods for
9、Notched Bar Impact Testing ofMetallic MaterialsE74 Practice of Calibration of Force-Measuring Instru-ments for Verifying the Force Indication of Testing Ma-chinesE 290 Test Methods for Bend Testing of Material forDuctilityG1 Practice for Preparing, Cleaning, and Evaluating Cor-rosion Test SpecimensG
10、4 Guide for Conducting Corrosion Tests in Field Appli-cationsG15 Terminology Relating to Corrosion and CorrosionTestingG16 Guide for Applying Statistics to Analysis of CorrosionDataG46 Guide for Examination and Evaluation of PittingCorrosionG69 Test Method for Measurement of Corrosion Potentialsof A
11、luminum Alloys3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 absorbera boron-based neutron-absorbing materialsystem.3.1.2 confirmation teststests that may be necessary toconfirm the continued presence and integrity of the neutronabsorber.1This guide is under the jurisdiction
12、of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.03 on Neutron AbsorberMaterials Specifications.Current edition approved July 1, 2007. Published August 2007. Originallyapproved in 1991. Last previous edition approved in 1999 as C 1187 91 (1999).2For ref
13、erenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, We
14、st Conshohocken, PA 19428-2959, United States.3.1.3 high-density storagethe close-packing of spent fuelto the extent that absorbers are required for neutron fluxreduction to assure adequate sub-criticality margin.3.1.4 irradiation (flux)the incidence of neutron andgamma radiation from spent-fuel ass
15、emblies on materials in awater-filled spent fuel pool.3.1.5 neutron attenuation testfor neutron absorber mate-rials, a process in which a material is placed in a thermalneutron beam, and the number of neutrons transmitted throughthe material in a specified period of time is counted. Theneutron count
16、 can be converted to areal density by performingthe same test on a series of appropriate calibration standardsand comparing the results. This definition is applicable toin-situ testing of neutron absorber materials or the testing ofsurveillance coupons.33.1.6 neutron blackness testa qualitative test
17、 using aneutron source for locating any unshielded areas within anabsorber.3.1.7 sampleone or more specimens of the absorberselected by some predetermined sampling process.3.1.8 service lifethe period of time for which properties ofthe absorber are expected to remain in compliance within thedesign s
18、pecifications.3.1.9 specimenan individual full-size piece of the ab-sorber or any portion thereof selected and prepared as neces-sary for test purposes.4. Significance and Use4.1 The storage of nuclear fuel in high-density storage racksis dependent upon the presence and performance of an absorberbet
19、ween the stored fuel assemblies to ensure that the reactivityof the storage configuration does not exceed the K-effectiveallowed by applicable regulations. A confirmation test may berequired to verify the presence and performance of the absorberwithin the racks. When the absorbers are not visible or
20、accessible for inspection (such as being fixed within the wallsof the structure surrounding the storage position in the rack) asurveillance test program may be conducted on representativespecimens of the absorber that are accessible and exposed tothe same environmental factors as those in the rack.4
21、.2 This guide provides guidance for establishing and con-ducting a surveillance program for monitoring the ongoingperformance of the absorbers.5. Characteristics to be Monitored5.1 The primary function of the absorber is to providesufficient total-removal cross section for thermal neutronsthroughout
22、 the relatively high (neutron) flux region betweenthe active zones of adjacent fuel assemblies. The most impor-tant characteristic to be monitored is the ability of the absorberto continuously and effectively remove thermal neutrons. Thischaracteristic may vary over time after exposure to the heat,r
23、adiation, water chemistry, and mechanical forces experiencedby the racks from the storage of nuclear fuel.5.1.1 The metal-based absorbers may be monitored forverification of adequate neutron absorbing capability by peri-odic neutron attenuation tests or neutron blackness tests, orboth. They may also
24、 be monitored for radiation damage,corrosion effects or other types of deterioration that reduce thephysical integrity or neutron performance of the absorbersbelow the predetermined limits for the design service life of theracks (see 8.3).5.1.2 The polymer-based absorbers may require augmentedmonito
25、ring over and above periodic specimen surveillance byperiodic neutron attenuation tests or neutron blackness tests, orboth.4The monitoring may also include consideration ofradiation damage or other types of deterioration that mayreduce the physical integrity or neutron performance of theabsorber bel
26、ow the predetermined limits for the design servicelife of the racks (see 8.3).6. Surveillance Specimens6.1 Wherever possible, the design of surveillance specimensshall be in accordance with the requirements of ASTM testmethods for the specific properties of interest to be measured.The size and confi
27、guration of certain specimens may berepresentative of those contained in the racks (see 6.1.2)inevery respect possible, and yet be retrievable from the repre-sentative exposure areas of the racks at periodic intervals. Thesize and configuration of the specimens shall be appropriate formonitoring tho
28、se characteristics where changes may be antici-pated such as corrosion effects, radiation shrinkage, or degra-dation of the physical properties. It is recommended thatarchive (benchmark) specimens be retained for the duration ofthe surveillance program. In all cases, the exposed and nonex-posed (arc
29、hive) specimens shall be of the same size and shape.The pre-characterization of specimens shall be performed withrespect to the important parameters.6.1.1 The specimens for the metal-based absorbers shall besuitable for neutron attenuation testing, weight gain (due tocorrosion), and dimensional chan
30、ges due to pitting, cracking orblistering.6.1.2 The specimens for the polymer-based absorber shallbe suitable for neutron attenuation testing, and the specimensshall be large enough to obtain practical radiation shrinkage/cracking and other test data.7. Measurement Methods and Frequencies7.1 The sel
31、ection and qualification of measurement methodsshall be in accordance with Guide C 1068 and in compliancewith all regulatory requirements and with the recommendationsof 6.1.1 and 6.2 of Specification C 992 as deemed appropriate.The frequency of measurements shall be determined based onthe previous s
32、ite measurements, experience at other similarsites, and from published data on the particular absorber, or any3Pierce, T.B., “Some uses of neutrons from non-reactor sources for theexamination of metals and allied materials,” IAEA-SM-159/17, pp. 4961.4Lindquist, K. et al., “Radiation induced changes
33、in the physical properties ofBoraflexTM a neutron absorber material for nuclear applications,” J. NuclearMaterials, 217 (1994), 223225.C1187072of the three.5Acceptance criteria shall be established for eachof the measurement methods selected prior to implementing asurveillance program.7.1.1 Neutron
34、Absorber PerformanceThe quantitativemeasurement of the performance of an absorber requires aneutron source and sensitive neutron detection devices. Thetest specimen of neutron absorber material shall meet or exceedthe required absorber areal density as specified in the designspecification or Safety
35、Analysis Report (SAR). Measurementerror and uncertainty shall be considered.7.1.2 Physical CharacteristicsPhysical characteristicsshall be measured in accordance with generally acceptedpractices in the nuclear industry. The test specimen shall meetthe minimum required physical characteristics as spe
36、cified inthe design specification or Safety Analysis Report. Measure-ment error and uncertainty shall be considered.7.1.3 Mechanical CharacteristicsMechanical tests shallbe performed commensurate with the duty expected of theabsorber. Consideration shall be given to the expected perfor-mance life of
37、 the neutron absorber, normal, off normal andaccident conditions and whether the absorber performs in aload bearing or non-load bearing role. The mechanical require-ments of the absorber should be reflected in the designspecification and SAR. When required, mechanical character-istics of the metal-b
38、ased absorber shall be assessed in accor-dance with procedures such as Definitions E6, Test MethodsE8 and E45, Practice E74 and Test Method E 290. Whenrequired, mechanical characteristics of the polymer-based ab-sorber shall be measured in accordance with procedures suchas Test Methods D 412, D 430,
39、 D 518, D 813, D 1415, D 2240,Practices D 3183 and D 4483.7.1.4 Corrosion CharacteristicsCoupons shall be exam-ined for corrosion; the rate and type of corrosion will beevaluated for the effect on the ability of the neutron absorber toperform its design functions for the intended lifetime. Thecorros
40、ion performance requirements of the absorber should bereflected in the design specification and SAR. Corrosioncharacteristics of the metal-based absorber shall be assessed inaccordance with procedures such as Practice G1, Guide G4,Definitions G15, Practices G 16, G 46 and G 69.8. Records and Reporti
41、ng8.1 Collection, storage, and control of records required bythis guide shall be in accordance with the requirements of therelevant regulations and appropriate specifications.8.2 A report is required. It shall include the followingsurveillance program description and other information, andprovide bo
42、th SI units and conventional units as applicable:8.2.1 ProgramThe location and duration of the surveil-lance specimens with respect to the proximity, burn-up and ageof the spent fuel assemblies, and any other pertinent environ-mental parameters shall be provided.8.2.2 Sample DescriptionA description
43、 of surveillancesamples, including such information as configuration, fabrica-tion history, material certifications, chemical analysis, physicalanalysis, and any other pertinent data shall be provided.8.2.3 Test ScheduleA test schedule shall be providedshowing the exposure period and test locations
44、for each of thesurveillance specimens so the accumulated exposure time andtotal radiation doses for each specimen are known and con-trolled in accordance with the surveillance program.8.2.4 Test ResultsThe test results of all measurementstaken shall be recorded and compared against the originalbasel
45、ine and predicted data.8.2.5 Test ConclusionsAn objective assessment of the testresults shall be given and a statement made to the effect that theperformance of the absorbers are or are not expected to meetthe stated performance criteria for the design service-lifeperiod (see 3.1.1.6 and section 4.1
46、.1 of Specification C 992).8.3 Additional CommentsAny additional information,such as test or calculation uncertainties, time-history of poolwater chemistry and any known excursions from the baselineconditions, that would be pertinent to the purpose of thesurveillance testing shall be reported.9. Key
47、words9.1 boron-based neutron-absorbing material systems; high-density storage; irradiation; metal-based; neutron attenuation;neutron blackness; neutron flux; polymer-based; reactivity;service life; surveillance.ASTM International takes no position respecting the validity of any patent rights asserte
48、d in connection with any item mentionedin this standard. Users of this standard are expressly advised that determination of the validity of any such patent rights, and the riskof infringement of such rights, are entirely their own responsibility.This standard is subject to revision at any time by th
49、e responsible technical committee and must be reviewed every five years andif not revised, either reapproved or withdrawn. Your comments are invited either for revision of this standard or for additional standardsand should be addressed to ASTM International Headquarters. Your comments will receive careful consideration at a meeting of theresponsible technical committee, which you may attend. If you feel that your comments have not received a fair hearing you shouldmake your views known to the ASTM Committee on Standards, at the address shown below.This sta
