ASTM C1187-2015 Standard Guide for Establishing Surveillance Test Program for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks In a Pool Environ.pdf

1、Designation: C1187 15Standard Guide forEstablishing Surveillance Test Program for Boron-BasedNeutron Absorbing Material Systems for Use in Nuclear FuelStorage Racks In a Pool Environment1This standard is issued under the fixed designation C1187; the number immediately following the designation indic

2、ates the year 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 () indicates an editorial change since the last revision or reapproval.1. Scope1.1 This guide provides guidance for establishi

3、ng a surveil-lance test program to monitor the performance of boron-basedneutron absorbing material systems (absorbers) necessary tomaintain sub-criticality in nuclear fuel storage racks in a poolenvironment. The practices presented in this guide, whenimplemented, will provide a comprehensive survei

4、llance testprogram to verify the functionality and integrity of the neutronabsorbing material within the storage racks. The performanceof a surveillance test program provides added assurance of thesafe and effective operation of a high-density storage facilityfor nuclear fuel. There are several diff

5、erent techniques forsurveillance testing of boron-based neutron absorbing materi-als. This guide focuses on coupon monitoring and in-situtesting.1.2 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this stand

6、ard 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:2C992 Specification for Boron-Based Neutron AbsorbingMaterial Systems for Use in Nuclear Spent Fuel StorageRacksC1068 Guide for

7、Qualification of Measurement Methods bya Laboratory Within the Nuclear IndustryD412 Test Methods for Vulcanized Rubber and Thermoplas-tic ElastomersTensionD430 Test Methods for Rubber DeteriorationDynamicFatigueD518 Test Method for Rubber DeteriorationSurfaceCracking (Withdrawn 2007)3D813 Test Metho

8、d for Rubber DeteriorationCrack GrowthD1415 Test Method for Rubber PropertyInternationalHardnessD2240 Test Method for Rubber PropertyDurometer Hard-nessD3183 Practice for RubberPreparation of Pieces for TestPurposes from ProductsD4483 Practice for Evaluating Precision for Test MethodStandards in the

9、 Rubber and Carbon Black ManufacturingIndustriesE6 Terminology Relating to Methods of Mechanical TestingE8 Test Methods for Tension Testing of Metallic MaterialsE23 Test Methods for Notched Bar Impact Testing of Me-tallic MaterialsE45 Test Methods for Determining the Inclusion Content ofSteelE74 Pra

10、ctice of Calibration of Force-Measuring Instrumentsfor Verifying the Force Indication of Testing MachinesE290 Test Methods for Bend Testing of Material for Ductil-ityE2971 Test Method for Determination of Effective Boron-10Areal Density in Aluminum Neutron Absorbers usingNeutron Attenuation Measurem

11、entsG1 Practice for Preparing, Cleaning, and Evaluating Corro-sion Test SpecimensG4 Guide for Conducting Corrosion Tests in Field Applica-tionsG15 Terminology Relating to Corrosion and Corrosion Test-ing (Withdrawn 2010)3G16 Guide for Applying Statistics to Analysis of CorrosionDataG46 Guide for Exa

12、mination and Evaluation of Pitting Cor-rosionG69 Test Method for Measurement of Corrosion Potentialsof Aluminum Alloys1This guide is under the jurisdiction of ASTM Committee C26 on Nuclear FuelCycle and is the direct responsibility of Subcommittee C26.03 on Neutron AbsorberMaterials Specifications.C

13、urrent edition approved June 1, 2015. Published July 2015. Originally approvedin 1991. Last previous edition approved in 2007 as C1187 07. DOI: 10.1520/C1187-15.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book o

14、f ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3The last approved version of this historical standard is referenced onwww.astm.org.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States13.

15、 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 functionality and integrity of the neutronabsorber.3.1.3 degradationa change in a material property

16、thatlessens the original design functionality.3.1.4 high-density storagethe close-packing of fuel to theextent that absorbers are required for neutron flux reduction toassure adequate sub-criticality margin.3.1.5 in-situ neutron attenuation testa qualitative or quan-titative test using a neutron sou

17、rce for determining neutronabsorbing functionalities.3.1.6 in-situ testremote characterization of absorber ma-terial in the storage racks.3.1.7 irradiation (flux)the incidence of neutron andgamma radiation from fuel assemblies on materials in awater-filled fuel pool.3.1.8 neutron attenuation testfor

18、 neutron absorbermaterials, 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 can be converted to areal density by performingthe same test on a series of appropriate

19、calibration standardsand comparing the results. This definition is applicable toin-situ testing of neutron absorber materials or the testing ofsurveillance coupons.43.1.9 sampleone or more specimens of the absorber se-lected by some predetermined sampling process.3.1.10 service lifethe period of tim

20、e for which propertiesof the absorber are expected to remain in compliance within thedesign specifications.3.1.11 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

21、 in high-density storage racksis dependent upon the functionality and integrity of an absorberbetween 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 th

22、e functionality and integrity of the absorberwithin the racks. If establishing a surveillance program fornewly installed or existing absorber material in fuel racks, thefollowing methods are suggested: (a) coupon monitoringprogram (if coupons are available); (b) in-situ neutron attenu-ation test; an

23、d (c) other applicable in-situ tests such as visualinspection or drag test.4.2 This guide provides guidance for establishing and con-ducting a surveillance program for monitoring the ongoingfunctionality and integrity of the absorbers.5. Characteristics to be Monitored5.1 The primary function of the

24、 absorber is to providesufficient absorption cross section for thermal neutronsthroughout 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 re

25、move thermal neutrons. Thischaracteristic may vary over time after exposure to the heat,radiation, water chemistry, and mechanical forces experiencedby the racks from the storage of nuclear fuel or naturalphenomena, or both.5.1.1 Absorbers should be monitored for verification ofadequate neutron abso

26、rbing functionality by periodic neutronattenuation tests of removable surveillance specimens, in-situneutron attenuation tests, or both.5.1.2 Absorbers characterization should include consider-ation of radiation damage or other types of deterioration thatmay reduce the physical integrity or function

27、ality of theabsorber below the predetermined limits for the design servicelife of the racks (see 8.3).6. Surveillance Specimens6.1 Wherever possible, the design of surveillance specimensshould be in accordance with the requirements of ASTMstandards for the specific properties of interest to be measu

28、red.The size and configuration of certain specimens should berepresentative of the absorbers contained in the racks (see6.1.2) in every respect possible, and the conditions to which thespecimens are exposed should be representative of the envi-ronmental factors existing in the rack. The specimens sh

29、ouldbe configured such that they are retrievable from the represen-tative exposure areas of the racks at periodic intervals. The sizeand configuration of the specimens should be appropriate formonitoring those characteristics where changes may be antici-pated such as corrosion effects, radiation shr

30、inkage, 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 non-exposed (archive) specimens shall be of the same size andshape. The pre-characterization of specimens sha

31、ll be per-formed with respect to the parameters of importance tofunctionality.6.1.1 The specimens for the metal-based absorbers shall besuitable for neutron attenuation testing, weight change (due todegradation), and changes including pitting, cracking, andblistering.6.1.2 The specimens for the poly

32、mer-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 selection and qualification of measurement methodsshall be in accordance with

33、 Guide C1068 and in compliance4Pierce, T. B., “Some uses of neutrons from non-reactor sources for theexamination of metals and allied materials,” IAEA-SM-159/17, pp. 4961.C1187 152with all regulatory requirements and with the recommendationsof 6.1.1 and 6.2 of Specification C992 as appropriate. Thef

34、requency of measurements shall be determined based on theprevious site measurements, experience at other similar sites,and from published data on the particular absorber, as avail-able.5Acceptance criteria shall be established for key charac-teristics that are selected prior to implementing a survei

35、llanceprogram. Acceptance criteria are established by the designerfor approval by the owner and regulating authorities.7.1.1 Neutron Absorber PerformanceThe quantitativemeasurement of the performance of an absorber requires aneutron source and sensitive neutron detection devices. Thetest specimen of

36、 neutron absorber material shall meet therequired absorber areal density as specified in the designspecification such as the Safety Analysis Report (SAR). Mea-surement error and uncertainty shall be considered. The speci-mens should be tested in accordance with Test Method E2971.7.1.2 Physical Chara

37、cteristicsPhysical characteristicsshall be measured in accordance with generally acceptedpractices in the nuclear industry. The test specimen shall meetthe minimum required physical characteristics as specified inthe design specification such as the Safety Analysis Report.Measurement error and uncer

38、tainty shall be considered. Somephysical characteristics may be determined by in-situ tests suchas visual inspection.7.1.3 Mechanical CharacteristicsMechanical tests shallbe performed commensurate with the functionality expected ofthe absorber. Consideration shall be given to the expectedservice lif

39、e of 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 such as the SAR. When required, mechanicalcharacteristics of

40、the metal-based absorber shall be assessed inaccordance with procedures such as Terminology E6, TestMethods E8 and E45, Practice E74 and Test Method E290.When required, mechanical characteristics of the polymer-based absorber should be measured in accordance with proce-dures such as Test Methods D41

41、2, D430, D518, D813, D1415,D2240, Practices D3183 and D4483. Some mechanical char-acteristics may be determined by in-situ tests.7.1.4 Corrosion CharacteristicsCoupons should be exam-ined for corrosion; the rate and type of corrosion will beevaluated for the effect on the ability of the neutron abso

42、rber toperform its design functions for the intended service life. Thecorrosion performance requirements of the absorber should bereflected in the design specification such as the SAR. Corrosioncharacteristics of the metal-based absorber shall be assessed inaccordance with procedures such as Practic

43、e G1, Guide G4,Terminology G15, Practices G16, G46 and G69. Corrosioncharacteristics cannot be determined by in-situ tests.8. Records and Reporting8.1 Collection, storage, and control of records required bythis guide shall be in accordance with the requirements of therelevant regulations and appropr

44、iate specifications.8.2 A report is required. It shall include the followingsurveillance program description and other information, andprovide both 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-

45、up and ageof the fuel assemblies, and any other pertinent environmentalparameters shall be provided.8.2.2 Sample DescriptionA description of surveillancesamples, including such information as configuration, fabrica-tion history, material certifications, chemical analysis, physicalanalysis, and any o

46、ther pertinent data shall be provided.8.2.3 Test ScheduleA test schedule shall be providedshowing the exposure period and test locations 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

47、surveillance program.8.2.4 Test ResultsThe test results of all measurementstaken shall be recorded and compared against the originalbaseline and predicted data. Measurement error and uncer-tainty shall be considered. Data trending shall be reported asappropriate.8.2.5 Test ConclusionsAn objective as

48、sessment of the testresults shall be given and a statement made to the effect that theperformance of the absorbers is or is not expected to meet thestated performance criteria for the design service life period(see 3.1.6 and section 4.1.1 of Specification C992).8.3 Additional CommentsAny additional

49、information,such as test or calculational biases, time-history of pool waterchemistry and any known excursions from the baselineconditions, that would be pertinent to the purpose of thesurveillance testing shall be reported.9. Keywords9.1 boron-based neutron absorbing material systems; cou-pon monitoring program; high-density fuel storage racks;in-situ tests; irradiation; metal-based; neutron absorber; neu-tron attenuation; polymer-based; reactivity; service life; sur-veillance.5Insoo Jun and Myung Jae Song, “Nuclear Analysis for the Boraflex Used in aTy