ASTM E482-11

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

SIGNIFICANCE AND USE
The neutronics methodology is validated, if (in addition to qualitative model evaluation) all of the following criteria are satisfied:
(1) The bias, q¯, is less than ε1
General:  
The methodology recommended in this guide specifies criteria for validating computational methods and outlines procedures applicable to pressure vessel related neutronics calculations for test and power reactors. The material presented herein is useful for validating computational methodology and for performing neutronics calculations that accompany reactor vessel surveillance dosimetry measurements (see Master Matrix E706 and Practice E853). Briefly, the overall methodology involves: (1) methods-validation calculations based on at least one well-documented benchmark problem, and (2) neutronics calculations for the facility of interest. The neutronics calculations of the facility of interest and of the benchmark problem should be performed consistently, with important modeling parameters kept the same or as similar as is feasible. In particular, the same energy group structure and common broad-group microscopic cross sections should be used for both problems. The neutronics calculations involve two tasks: (1) determination of the neutron source distribution in the reactor core by utilizing diffusion theory (or transport theory) calculations in conjunction with reactor power distribution measurements, and (2) performance of a fixed fission rate neutron source (fixed-source) transport theory calculation to determine the neutron fluence rate distribution in the reactor core, through the internals and in the pressure vessel. Some neutronics modeling details for the benchmark, test reactor, or the power reactor calculation will differ; therefore, the procedures described herein are general and apply to each case. (See NUREG/CR–5049, NUREG/CR–1861, NUREG/CR–3318, and NUREG/CR–3319.)
It is expected that transport calculations will be performed whenever pressure vessel surveillance dosimetry...
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 E944 and Practice E853 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: 31-May-2011
• ICS: 75.080 - Petroleum products in general
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E482-07 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• Effective Date: 01-Jun-2011
• Replaced By: ASTM E482-11e1 - Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
• Effective Date: 01-Jun-2011
• 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-2011
• Referred By: ASTM E944-19 - Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
• Effective Date: 01-Jun-2011
• Referred By: ASTM E185-21 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jun-2011
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jun-2011
• 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-2011
• Referred By: ASTM E1854-19 - Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
• Effective Date: 01-Jun-2011
• Referred By: ASTM E900-21 - Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
• Effective Date: 01-Jun-2011
• Referred By: ASTM E1035-18(2023) - Standard Practice for Determining Neutron Exposures for Nuclear Reactor Vessel Support Structures
• Effective Date: 01-Jun-2011
• Referred By: ASTM E1018-20e1 - Standard Guide for Application of ASTM Evaluated Cross Section Data File
• Effective Date: 01-Jun-2011
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 01-Jun-2011
• Referred By: ASTM E1006-21 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
• Effective Date: 01-Jun-2011
• Referred By: ASTM E2956-23 - Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
• 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-2011

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 − 11
StandardGuide 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 Reactor Surveillance Results, E706(IA)
E944 Guide for Application of Neutron Spectrum Adjust-
1.1 Need for Neutronics Calculations—An accurate calcu-
ment Methods in Reactor Surveillance, E 706 (IIA)
lation of the neutron fluence and fluence rate at several
E1018 Guide for Application of ASTM Evaluated Cross
locations is essential for the analysis of integral dosimetry
Section Data File, Matrix E706 (IIB)
measurements and for predicting irradiation damage exposure
E2006 Guide for Benchmark Testing of Light Water Reactor
parameter values in the pressure vessel. Exposure parameter
Calculations
values may be obtained directly from calculations or indirectly
4
2.2 Nuclear Regulatory Documents:
from calculations that are adjusted with dosimetry measure-
NUREG/CR-1861 LWR Pressure Vessel Surveillance Do-
ments; Guide E944 and Practice E853 define appropriate
simetry Improvement Program: PCA Experiments and
computational procedures.
Blind Test
1.2 Methodology—Neutronics calculations for application
NUREG/CR-3318 LWR Pressure Vessel Surveillance Do-
to reactor vessel surveillance encompass three essential areas:
simetry Improvement Program: PCA Experiments, Blind
(1) validation of methods by comparison of calculations with
Test, and Physics-Dosimetry Support for the PSF Experi-
dosimetry measurements in a benchmark experiment, (2)
ments
determination of the neutron source distribution in the reactor
NUREG/CR-3319 LWR Pressure Vessel Surveillance Do-
core, and (3) calculation of neutron fluence rate at the surveil-
simetry Improvement Program: LWR Power Reactor Sur-
lance position and in the pressure vessel.
veillance Physics-Dosimetry Data Base Compendium
1.3 This standard does not purport to address all of the
NUREG/CR-5049 Pressure Vessel Fluence Analysis and
safety concerns, if any, associated with its use. It is the
Neutron Dosimetry
responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica-
3. Significance and Use
bility of regulatory requirements prior to use.
3.1 General:
3.1.1 Themethodologyrecommendedinthisguidespecifies
2. Referenced Documents
criteria for validating computational methods and outlines
2
2.1 ASTM Standards:
procedures applicable to pressure vessel related neutronics
E706 MasterMatrixforLight-WaterReactorPressureVessel
calculationsfortestandpowerreactors.Thematerialpresented
3
Surveillance Standards, E 706(0) (Withdrawn 2011)
herein is useful for validating computational methodology and
E844 Guide for Sensor Set Design and Irradiation for
for performing neutronics calculations that accompany reactor
Reactor Surveillance, E 706 (IIC)
vessel surveillance dosimetry measurements (see Master Ma-
E853 Practice forAnalysis and Interpretation of Light-Water
trix E706 and Practice E853). Briefly, the overall methodology
involves: (1) methods-validation calculations based on at least
one well-documented benchmark problem, and (2) neutronics
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
calculations for the facility of interest. The neutronics calcula-
Technology and Applications and is the direct responsibility of Subcommittee
tions of the facility of interest and of the benchmark problem
E10.05 on Nuclear Radiation Metrology.
should be performed consistently, with important modeling
Current edition approved June 1, 2011. Published June 2011. Originally
parameters kept the same or as similar as is feasible. In
approved in 1976. Last previous edition approved in 2007 as E482 – 07 DOI:
10.1520/E0482-11.
particular, the same energy group structure and common
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
broad-group microscopic cross sections should be used for
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
The last approved version of this historical standard is referenced on Available from Superintendent of Documents, U.S. Government Printing
www.astm.org. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E482 − 11
both problems. The neutronics calculations involv
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:E 482–89(Reapproved 1996) Designation: E482 – 11
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 (ϵ) indicates an editorial change since the last revision or reapproval.
1. 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 944E944 and Practice E 853E853 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 may involve hazardous materials, operations, and equipment. 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 limitationsrequirements prior to use.
2. Referenced Documents
2.1 ASTM Standards:
E170Terminology Relating to Radiation Measurements and Dosimetry
2
E560Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706(IC)
E693Practice for Characterizing Neutron Exposures in Iron and LowAlloy Steels in Terms of Displacements PerAtom (DPA),
2 2
E706(ID)
2
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0) E 706(0)
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
2
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA) E706(IA)
2
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)
2
E1018Guide for Application of ASTM Evaluated Cross Section Data File (ENDF/A), E706(IIB)
E706(IE)Damage Correlation for Reactor Vessel Surveillance
3
E706(IIE)Benchmark Testing of Reactor Vessel Dosimetry Guide for Application of Neutron Spectrum Adjustment Methods
in Reactor Surveillance, E 706 (IIA)
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
E2006 Guide for Benchmark Testing of Light Water Reactor Calculations
3
2.2 Nuclear Regulatory Documents:
NUREG/CR-1861 LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PCA Experiments and Blind Test
NUREG/CR-3318 LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PCA Experiments, Blind Test, and
Physics-Dosimetry Support for the PSF Experiments
NUREG/CR-3319 LWR Pressure Vessel Surveillance Dosimetry Improvement Program: LWR Power Reactor Surveillance
Physics-Dosimetry Data Base Compendium
NUREG/CR-5049 Pressure Vessel Fluence Analysis and Neutron Dosimetry
1
This guide is under the jurisdiction of ASTM Committee E-10 E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05
on Nuclear Radiation Metrology.
1
Current edition approved Oct. 27, 1989. Published December 1989. Originally published as E 482–76. Last previous edition E 482–82ϵ .
Current edition approved June 1, 2011. Published June 2011. Originally approved in 1976. Last previous edition approved in 2007 as E482 – 07 DOI: 10.1520/E0482-11.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
, Vol 12.02.volume information, refer to the standard’s Document Summary page on the ASTM website.
3
For standards that are in the draft stage and have not received an ASTM designation, see Section 5, as well as, Figures 1 and 2 of Matrix E 706E 706.
3
Available from Superintendent of Documents, U.S. Government Printing Office, Washington, DC 20402.
Copyright © ASTM Interna
...