ASTM E482-01

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.
1.3 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: 09-Jun-2001
• 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 E482-89(1996) - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• Effective Date: 10-Jun-2001
• Replaced By: ASTM E482-07 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• 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: 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 E1018-20e1 - Standard Guide for Application of ASTM Evaluated Cross Section Data File
• Effective Date: 10-Jun-2001
• Referred By: ASTM E2232-21 - Standard Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications
• 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 E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• Effective Date: 10-Jun-2001
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 10-Jun-2001
• Referred By: ASTM E185-21 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 10-Jun-2001
• Referred By: ASTM E2005-21 - Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
• Effective Date: 10-Jun-2001
• Referred By: ASTM E944-19 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
• Effective Date: 10-Jun-2001
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 10-Jun-2001
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• 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

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:E482–01
Standard Guide for
Application of Neutron Transport Methods for Reactor
1
Vessel Surveillance, E706 (IID)
This standard is issued under the fixed designation E 482; 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 E 853 Practice for Analysis and Interpretation of Light-
2
Water Reactor Surveillance Results, E706 (IA)
1.1 Need for Neutronics Calculations—An accurate calcu-
E 944 Guide for Application of Neutron Spectrum Adjust-
lation of the neutron fluence and fluence rate at several
2
ment Methods in Reactor Surveillance, E706 (IIA)
locations is essential for the analysis of integral dosimetry
E 1018 Guide for Application of ASTM Evaluated Cross
measurements and for predicting irradiation damage exposure
2
Section Data File, E706(IIB)
parameter values in the pressure vessel. Exposure parameter
E 2005 Guide for the Benchmark Testing of Reactor Do-
values may be obtained directly from calculations or indirectly
simetry in Standard and Reference Neutron Fields E706
from calculations that are adjusted with dosimetry measure-
2
(IIE-1)
ments; Guide E 944 and Practice E 853 define appropriate
E 2006 Guide for the Benchmark Testing of LWR Calcula-
computational procedures.
2
tions E706 (IIE-2)
1.2 Methodology—Neutronics calculations for application
3
2.2 Nuclear Regulatory Documents:
to reactor vessel surveillance encompass three essential areas:
NUREG/CR-1861 LWR Pressure Vessel Surveillance Do-
(1) validation of methods by comparison of calculations with
simetry Improvement Program: PCA Experiments and
dosimetry measurements in a benchmark experiment, (2)
Blind Test
determination of the neutron source distribution in the reactor
NUREG/CR-3318 LWR Pressure Vessel Surveillance Do-
core, and (3) calculation of neutron fluence rate at the surveil-
simetry Improvement Program: PCA Experiments, Blind
lance position and in the pressure vessel.
Test, and Physics-Dosimetry Support for the PSF Experi-
1.3 This standard does not purport to address all of the
ments
safety concerns, if any, associated with its use. It is the
NUREG/CR-3319 LWR Pressure Vessel Surveillance Do-
responsibility of the user of this standard to establish appro-
simetry Improvement Program: LWR Power Reactor Sur-
priate safety and health practices and determine the applica-
veillance Physics-Dosimetry Data Base Compendium
bility of regulatory requirements prior to use.
NUREG/CR-5049 Pressure Vessel Fluence Analysis and
2. Referenced Documents
Neutron Dosimetry
2.1 ASTM Standards:
3. Significance and Use
E 170 Terminology Relating to Radiation Measurements
2
3.1 General:
and Dosimetry
3.1.1 Themethodologyrecommendedinthisguidespecifies
E 560 Practice for Extrapolating Reactor Vessel Surveil-
2
criteria for validating computational methods and outlines
lance Dosimetry Results, E706(IC)
procedures applicable to pressure vessel related neutronics
E 693 Practice for Characterizing Neutron Exposures in
calculationsfortestandpowerreactors.Thematerialpresented
Iron and Low Alloy Steels in Terms of Displacements Per
2 herein is useful for validating computational methodology and
Atom (DPA), E706(ID)
for performing neutronics calculations that accompany reactor
E 706 Master Matrix for Light-Water Reactor Pressure
2
vessel surveillance dosimetry measurements (see Master Ma-
Vessel Surveillance Standards, E706(0)
trix E 706 and Practice E 853). Briefly, the overall methodol-
E 844 Guide for Sensor Set Design and Irradiation for
2
ogy involves: (1) methods-validation calculations based on at
Reactor Surveillance, E706(IIC)
least one well-documented benchmark problem, and (2) neu-
tronics calculations for the facility of interest. The neutronics
calculations on the facility of interest and on the benchmark
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
problem should be as nearly the same as is feasible; in
Technology and Applications and is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
Current edition approved June 10, 2001. Published August 2001. Originally
3
published as E 482 – 76. Last previous edition E 482 – 89 (1996). Available from Superintendent of Documents, U.S. Government Printing
2
Annual Book of ASTM Standards, Vol 12.02. 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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E482
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