• There are no items in your cart
We noticed you’re not on the correct regional site. Switch to our AMERICAS site for the best experience.
Dismiss alert

ASTM E 1005 : 2016 : REDLINE

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance

Available format(s)

PDF

Superseded date

11-11-2021

Language(s)

English

Published date

01-10-2016

CONTAINED IN VOL. 12.02, 2016 Specifies procedures for measuring the specific activities of radioactive nuclides produced in radiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures.

1.1This test method describes procedures for measuring the specific activities of radioactive nuclides produced in radiometric monitors (RMs) by nuclear reactions induced during surveillance exposures for reactor vessels and support structures. More detailed procedures for individual RMs are provided in separate standards identified in 2.1 and in Refs (1-5).2 The measurement results can be used to define corresponding neutron induced reaction rates that can in turn be used to characterize the irradiation environment of the reactor vessel and support structure. The principal measurement technique is high resolution gamma-ray spectrometry, although X-ray photon spectrometry and Beta particle counting are used to a lesser degree for specific RMs (1-29).

1.1.1The measurement procedures include corrections for detector background radiation, random and true coincidence summing losses, differences in geometry between calibration source standards and the RMs, self absorption of radiation by the RM, other absorption effects, radioactive decay corrections, and burn out of the nuclide of interest (6-26).

1.1.2Specific activities are calculated by taking into account the time duration of the count, the elapsed time between start of count and the end of the irradiation, the half life, the mass of the target nuclide in the RM, and the branching intensities of the radiation of interest. Using the appropriate half life and known conditions of the irradiation, the specific activities may be converted into corresponding reaction rates (2-5, 28-30).

1.1.3Procedures for calculation of reaction rates from the radioactivity measurements and the irradiation power time history are included. A reaction rate can be converted to neutron fluence rate and fluence using the appropriate integral cross section and effective irradiation time values, and, with other reaction rates can be used to define the neutron spectrum through the use of suitable computer programs (2-5, 28-30).

1.1.4The use of benchmark neutron fields for calibration of RMs can reduce significantly or eliminate systematic errors since many parameters, and their respective uncertainties, required for calculation of absolute reaction rates are common to both the benchmark and test measurements and therefore are self canceling. The benchmark equivalent fluence rates, for the environment tested, can be calculated from a direct ratio of the measured saturated activities in the two environments and the certified benchmark fluence rate (2-5, 28-30).

1.2This method is intended to be used in conjunction with ASTM Guide E844. The following existing or proposed ASTM practices, guides, and methods are also directly involved in the physics-dosimetry evaluation of reactor vessel and support structure surveillance measurements:

E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706 (O) 3

E853 Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA)3

E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA), E706 (ID)3

E185 Practice for Conducting Surveillance Tests for Light-Water Nuclear Power Reactor Vessels, E706 (IF)3

E1035 Practice for Determining Radiation Exposure for Nuclear Reactor Vessel Support Structures, E706 (IG)3

E636 Practice for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)3

E2956 Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels3

E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E706 (IIA)3

E1018 Guide for Application of ASTM Evaluated Cross Section and Data File, E706 (IIB)3

E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)3

E2005 Guide for the Benchmark Testing of Reactor Vessel Dosimetry in Standard and Reference Neutron Fields

E2006 Guide for the Benchmark Testing of Light Water Reactor Calculations

E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Vessel Surveillance, E706 (IIIB)3

E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E706 (IIIC)3

E1214 Application and Analysis of Temperature Monitors for Reactor Vessel Surveillance, E706 (IIIE) 3

1.3The procedures in this test method are applicable to the measurement of radioactivity in RMs that satisfy the specific constraints and conditions imposed for their analysis. More detailed procedures for individual RM monitors are identified in 2.1 and in Refs 1-5 (see Table 1).

(A)The numbers in parentheses following some given values is the uncertainty in the last digit(s) of the value: 0.729 (8) means 0.729± 0.008, 70.8 (1) means 70.8 ± 0.1.
(B)NTR = Non-Threshold Response, TR = Threshold Response.
(C)The time units listed for half-life are years (a), days (d), hours (h), minutes (min), and seconds (s). Note that a “year” herein is considered to be tropical and equivalent to 365.242 days and thus equivalent to 31.556.926 s per Ref (31).
(D)The nuclear data has been drawn from several primary sources including Refs (31-34). Reference (35) summarizes the source of the selected nuclear constants, last checked for consistency on March 19, 2014.
(E)FM = Fission Monitor: 235U and 239Pu (NTR) and 238U, 237Np, and 232Th (TR) target isotope or weight fraction varies with material batch.

1.4This test method, along with the individual RM monitor standard methods, are intended for use by knowledgeable persons who are intimately familiar with the procedures, equipment, and techniques necessary to achieve high precision and accuracy in radioactivity measurements.

1.5The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard, except for the energy units based on the electron volt, keV and Mev, and the time units: minute (min), hour (h), day (d), and year (a).

1.6This 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.

Committee
E 10
DocumentType
Redline
Pages
13
PublisherName
American Society for Testing and Materials
Status
Superseded
SupersededBy

ASTM E 264 : 2008 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
ASTM E 266 : 2017 : REDLINE Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
ASTM E 704 : 2013 : REDLINE Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
ASTM E 844 : 2009 : R2014 : EDT 1 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
ASTM E 523 : 2016 : REDLINE Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
ASTM E 844 : 2009 : R2014 : EDT 2 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance
ISO 19226:2017 Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
ASTM E 1006 : 2013 : REDLINE Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
ASTM E 264 : 2008 : R2013 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Nickel
ASTM E 910 : 2018 : REDLINE Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
ASTM E 2956 : 2014 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
BS ISO 19226:2017 Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
ASTM E 261 : 2016 : REDLINE Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
ASTM E 393 : 2013 : REDLINE Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
ASTM E 706 : 2016 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE
ASTM E 1297 : 2008 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
17/30337935 DC : 0 BS ISO 19226 - NUCLEAR ENERGY - DETERMINATION OF NEUTRON FLUENCE AND DISPLACEMENTS PER ATOM (DPA) IN REACTOR VESSEL AND INTERNALS
ASTM E 1297 : 2008 : R2013 Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
ASTM E 1018 : 2009 : R2013 : EDT 1 Standard Guide for Application of ASTM Evaluated Cross Section Data File
ASTM E 1018 : 2009 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
ASTM E 1018 : 2009 : R2013 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)
ASTM E 343 : 1996 Standard Test Method for Measuring Reaction Rates by Analysis of Molybdenum-99 Radioactivity From Fission Dosimeters (Withdrawn 2002)
ASTM E 844 : 2009 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)

ASTM E 482 : 2016 : REDLINE Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
ASTM E 2956 : 2014 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
ASTM E 181 : 2017 : REDLINE Standard Test Methods for Detector Calibration and Analysis of Radionuclides
ASTM E 693 : 2017 : REDLINE Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
ASTM E 265 : 2015 : REDLINE Standard Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
ASTM E 262 : 2017 : REDLINE Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques
ASTM E 523 : 2016 : REDLINE Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper
ASTM E 266 : 2017 : REDLINE Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Aluminum
ASTM E 854 : 2014-12 TEST METHOD FOR APPLICATION AND ANALYSIS OF SOLID STATE TRACK RECORDER (SSTR) MONITORS FOR REACTOR SURVEILLANCE
IEEE/ANSI N42.14-1999 American National Standard for Calibration and Use of Germanium Spectrometers for the Measurement of Gamma-Ray Emission Rates of Radionuclides
ASTM E 704 : 2013 : REDLINE Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
ASTM E 261 : 2016 : REDLINE Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
ASTM E 2006 : 2016 : REDLINE Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 393 : 2013 : REDLINE Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
IEEE 645 : 1977 TEST PROCEDURES FOR HIGH-PURITY GERMANIUM DETECTORS FOR IONIZING RADIATION
ASTM E 185 : 2016 : REDLINE Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE
ASTM E 481 : 2016 : REDLINE Standard Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver

View more information
£70.87
Excluding VAT

Access your standards online with a subscription

Features

  • Simple online access to standards, technical information and regulations.

  • Critical updates of standards and customisable alerts and notifications.

  • Multi-user online standards collection: secure, flexible and cost effective.