ASTM E482-07

Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)

SCOPE
1.1 Need for Neutronics Calculations - An accurate calculation of the neutron fluence and fluence rate at several locations is essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are adjusted with dosimetry measurements; Guide E 944 and Practice E 853 define appropriate computational procedures.
1.2 Methodology Neutronics calculations for application to reactor vessel surveillance encompass three essential areas: (1) validation of methods by comparison of calculations with dosimetry measurements in a benchmark experiment, (2) determination of the neutron source distribution in the reactor core, and (3) calculation of neutron fluence rate at the surveillance position and in the pressure vessel.
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 requirements prior to use.

General Information

• Status: Historical
• Publication Date: 31-May-2007
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E482-01 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• Effective Date: 01-Jun-2007
• Replaced By: ASTM E482-11 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• Effective Date: 01-Jun-2011
• Referred By: ASTM E2005-21 - Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
• Effective Date: 01-Jun-2007
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 01-Jun-2007
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jun-2007
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 01-Jun-2007
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 01-Jun-2007
• Referred By: ASTM E1035-18(2023) - Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
• Effective Date: 01-Jun-2007
• Referred By: ASTM E185-21 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2007
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 01-Jun-2007
• Referred By: ASTM E1018-20e1 - Standard Guide for Application of ASTM Evaluated Cross Section Data File
• Effective Date: 01-Jun-2007
• Referred By: ASTM E944-19 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
• Effective Date: 01-Jun-2007
• Referred By: ASTM E910-18 - Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jun-2007
• Referred By: ASTM E2232-21 - Standard Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications
• Effective Date: 01-Jun-2007
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Jun-2007

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:E482–07
Standard Guide for
Application of Neutron Transport Methods for Reactor
1
Vessel Surveillance, E706 (IID)
This standard is issued under the fixed designation E482; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope E844 Guide for Sensor Set Design and Irradiation for
Reactor Surveillance, E 706(IIC)
1.1 Need for Neutronics Calculations—An accurate calcu-
E853 Practice for Analysis and Interpretation of Light-
lation of the neutron fluence and fluence rate at several
Water Reactor Surveillance Results, E706(IA)
locations is essential for the analysis of integral dosimetry
E944 Guide for Application of Neutron Spectrum Adjust-
measurements and for predicting irradiation damage exposure
ment Methods in Reactor Surveillance, E 706 (IIA)
parameter values in the pressure vessel. Exposure parameter
E1018 Guide for Application of ASTM Evaluated Cross
values may be obtained directly from calculations or indirectly
Section Data File, Matrix E706 (IIB)
from calculations that are adjusted with dosimetry measure-
E2006 Guide for Benchmark Testing of Light Water Reac-
ments; Guide E944 and Practice E853 define appropriate
tor Calculations
computational procedures.
4
2.2 Nuclear Regulatory Documents:
1.2 Methodology—Neutronics calculations for application
NUREG/CR-1861 LWR Pressure Vessel Surveillance Do-
to reactor vessel surveillance encompass three essential areas:
simetry Improvement Program: PCA Experiments and
(1) validation of methods by comparison of calculations with
Blind Test
dosimetry measurements in a benchmark experiment, (2)
NUREG/CR-3318 LWR Pressure Vessel Surveillance Do-
determination of the neutron source distribution in the reactor
simetry Improvement Program: PCA Experiments, Blind
core, and (3) calculation of neutron fluence rate at the surveil-
Test, and Physics-Dosimetry Support for the PSF Experi-
lance position and in the pressure vessel.
ments
1.3 This standard does not purport to address all of the
NUREG/CR-3319 LWR Pressure Vessel Surveillance Do-
safety concerns, if any, associated with its use. It is the
simetry Improvement Program: LWR Power Reactor Sur-
responsibility of the user of this standard to establish appro-
veillance Physics-Dosimetry Data Base Compendium
priate safety and health practices and determine the applica-
NUREG/CR-5049 Pressure Vessel Fluence Analysis and
bility of regulatory requirements prior to use.
Neutron Dosimetry
2. Referenced Documents
3. Significance and Use
2
2.1 ASTM Standards:
3.1 General:
E560 PracticeforExtrapolatingReactorVesselSurveillance
3
3.1.1 Themethodologyrecommendedinthisguidespecifies
Dosimetry Results, E 706(IC)
criteria for validating computational methods and outlines
E693 PracticeforCharacterizingNeutronExposuresinIron
procedures applicable to pressure vessel related neutronics
and LowAlloy Steels inTerms of Displacements PerAtom
calculationsfortestandpowerreactors.Thematerialpresented
(DPA), E 706(ID)
herein is useful for validating computational methodology and
E706 Master Matrix for Light-Water Reactor Pressure Ves-
for performing neutronics calculations that accompany reactor
sel Surveillance Standards, E 706(0)
vessel surveillance dosimetry measurements (see Master Ma-
trix E706 and Practice E853). Briefly, the overall methodology
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear involves: (1) methods-validation calculations based on at least
Technology and Applications and is the direct responsibility of Subcommittee
one well-documented benchmark problem, and (2) neutronics
E10.05 on Nuclear Radiation Metrology.
calculations for the facility of interest. The neutronics calcula-
CurrenteditionapprovedJune1,2007.PublishedJuly2007.Originallyapproved
tions on the facility of interest and on the benchmark problem
in 1976. Last previous edition approved in 2001 as E482 – 01. DOI: 10.1520/
E0482-07.
should be as nearly the same as is feasible; in particular, the
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
group structure and common broad-group microscopic cross
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website.
3 4
Withdrawn. The last approved version of this historical standard is referenced Available from Superintendent of Documents, U.S. Government Printing
on www.astm.org. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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