ASTM E1018-01

Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)

SCOPE
1.1 This guide covers the establishment and use of an ASTM evaluated nuclear data cross section and uncertainty file for analysis of single or multiple sensor measurements in neutron fields r
elated to LWR-Pressure Vessel Surveillance (PVS). These fields include in- and ex-vessel surveillance positions in operating power reactors, benchmark fields, and reactor test regions.
1.2 Requirements for establishment of ASTM-approved cross section files address data format, evaluation requirements, validation in benchmark fields, evaluation of error estimates (covariance file), and documentation. A further requirement for components of the ASTM-approved cross section file is their internal consistency when combined with sensor measurements and used to determine a neutron spectrum.
1.3 Specifications for use include energy region of applicability, data processing requirements, and application of uncertainties.
1.4 This guide is directly related to and should be used primarily in conjunction with Guides E 482 and E 944, and Practices E 560, E 185, and E 693.
1.5 The ASTM cross section and uncertainty file represents a generally available data set for use in sensor set analysis. However, the availability of this data set does not preclude the use of other validated data, either proprietary or nonproprietary.
1.6 This standard does not purport to address all of the safety concerns, 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

• Status: Historical
• Publication Date: 09-Jun-2001
• ICS: 35.240.50 - IT applications in industry
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E1018-95 - Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
• Effective Date: 10-Jun-2001
• Replaced By: ASTM E1018-09 - Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
• Effective Date: 01-Jun-2009
• Referred By: ASTM E264-19 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
• Effective Date: 10-Jun-2001
• Referred By: ASTM E1035-18(2023) - Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
• Effective Date: 10-Jun-2001
• Referred By: ASTM E263-18 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron
• Effective Date: 10-Jun-2001
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 10-Jun-2001
• Referred By: ASTM E526-22 - Standard Test Method for Measuring Fast-Neutron Reaction Rates By Radioactivation of Titanium
• Effective Date: 10-Jun-2001
• Referred By: ASTM E910-18 - Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
• Effective Date: 10-Jun-2001
• Referred By: ASTM E720-23 - Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics
• Effective Date: 10-Jun-2001
• Referred By: ASTM E523-21e1 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
• Effective Date: 10-Jun-2001
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 10-Jun-2001
• Referred By: ASTM E2006-22 - Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• Effective Date: 10-Jun-2001
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 10-Jun-2001
• Referred By: ASTM E704-19 - Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
• Effective Date: 10-Jun-2001
• Referred By: ASTM E721-22 - Standard Guide for Determining Neutron Energy Spectra from Neutron Sensors for Radiation-Hardness Testing of Electronics
• Effective Date: 10-Jun-2001

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:E1018–01
Standard Guide for
Application of ASTM Evaluated Cross Section Data File,
1
Matrix E706E706 (IIB)
This standard is issued under the fixed designation E1018; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 2. Referenced Documents
2
1.1 This guide covers the establishment and use of an 2.1 ASTM Standards:
ASTMevaluatednucleardatacrosssectionanduncertaintyfile E170 TerminologyRelatingtoRadiationMeasurementsand
2
for analysis of single or multiple sensor measurements in Dosimetry
neutron fields r E185 Practice for Design of Surveillance Programs for
2
elated to LWR-Pressure Vessel Surveillance (PVS). These Light-Water Moderated Nuclear Power Reactor Vessels
fields include in- and ex-vessel surveillance positions in E482 Guide forApplication of Neutron Transport Methods
2
operating power reactors, benchmark fields, and reactor test for Reactor Vessel Surveillance, E706 (IID)
regions. E560 PracticeforExtrapolatingReactorVesselSurveillance
32
1.2 Requirements for establishment of ASTM-approved Dosimetry Results, E 706(IC)
cross section files address data format, evaluation require- E693 PracticeforCharacterizingNeutronExposuresinIron
ments, validation in benchmark fields, evaluation of error andLowAlloySteelsinTermsofDisplacementsPerAtom
2
estimates (covariance file), and documentation. A further (DPA), E 706(ID)
requirement for components of the ASTM-approved cross E706 Master Matrix for Light-Water Reactor Pressure Ves-
2
section file is their internal consistency when combined with sel Surveillance Standards, E 706(0)
sensor measurements and used to determine a neutron spec- E844 Guide for Sensor Set Design and Irradiation for
2
trum. Reactor Surveillance, E 706(IIC)
1.3 Specifications for use include energy region of applica- E853 Practice for Analysis and Interpretation of Light-
2
bility, data processing requirements, and application of uncer- Water Reactor Surveillance Results, E706(IA)
tainties. E854 Test Method for Application and Analysis of Solid
1.4 This guide is directly related to and should be used State Track Recorder (SSTR) Monitors for Reactor Sur-
2
primarily in conjunction with Guides E482 and veillance, E706(IIIB)
E944E482E944, and Practices E560, E185, and E910 Test Method for Application and Analysis of Helium
E693E560E185E693. Accumulation Fluence Monitors for Reactor Vessel Sur-
2
1.5 TheASTM cross section and uncertainty file represents veillance, E706 (IIIC)
a generally available data set for use in sensor set analysis. E944 Guide for Application of Neutron Spectrum Adjust-
2
However, the availability of this data set does not preclude the ment Methods in Reactor Surveillance, E 706 (IIA)
use of other validated data, either proprietary or nonpropri- E1005 Test Method forApplication andAnalysis of Radio-
etary. metric Monitors for Reactor Vessel Surveillance, E
2
1.6 This standard does not purport to address all of the 706(IIIA)
safety concerns, if any, associated with its use. It is the E2005 Guide for Benchmark Testing of Reactor Dosimetry
2
responsibility of the user of this standard to establish appro- in Standard and Reference Neutron Fields
priate safety and health practices and determine the applica- E2006 Guide for Benchmark Testing of Light Water Reac-
bility of regulatory limitations prior to use. tor Calculations
3. Terminology
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
3.1 Definitions of Terms Specific to This Standard:
Technology and Applications and is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
2
Current edition approved June 10, 2001. Published September 2001. Originally Annual Book of ASTM Standards, Vol. 12.02.
3
published as E1018–84. Last previous edition E1018–95. DOI: 10.1520/E1018- Withdrawn. The last approved version of this historical standard is referenced
01. on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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E1018–01
3.1.1 benchmark field—a limited number of neutron fields 3.1.2 dosimetry cross sections—cross sections used for
have been identified as benchmark fields for the purpose of dosimetryapplicationandwhichprovidethetotalcrosssection
dosimetry sensor calibration and dosimetry cross section data for production of particular (measurable) reaction products.
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development and testing (1, 2,). These fields are permanent These include fission cross sections for production of fission
facilities in which experiments can be repeated. In add
...