ASTM E2006-05

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Designation:E2006–05
Standard Guide for
1
Benchmark Testing of Light Water Reactor Calculations
This standard is issued under the fixed designation E2006; 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 This guide covers general approaches for benchmarking
E944 Guide for Application of Neutron Spectrum Adjust-
neutron transport calculations in light water reactor systems.A
ment Methods in Reactor Surveillance, E 706 (IIA)
companion guide (Guide E2005) covers use of benchmark
E1018 Guide for Application of ASTM Evaluated Cross
fields for testing neutron transport calculations and cross
Section Data File, Matrix E706 (IIB)
sections in well controlled environments. This guide covers
E2005 Guide for Benchmark Testing of Reactor Dosimetry
experimental benchmarking of neutron fluence calculations (or
in Standard and Reference Neutron Fields
calculations of other exposure parameters such as dpa) in more
complex geometries relevant to reactor surveillance. Particular
3. Significance and Use
sections of the guide discuss: the use of well-characterized
3.1 This guide deals with the difficult problem of bench-
benchmark neutron fields to provide an indication of the
markingneutrontransportcalculationscarriedouttodetermine
accuracy of the calculational methods and nuclear data when
fluences for plant specific reactor geometries. The calculations
applied to typical cases; and the use of plant specific measure-
are necessary for fluence determination in locations important
ments to indicate bias in individual plant calculations. Use of
for material radiation damage estimation and which are not
these two benchmark techniques will serve to limit plant-
accessible to measurement. The most important application of
specific calculational uncertainty, and, when combined with
such calculations is the estimation of fluence within the reactor
analytical uncertainty estimates for the calculations, will pro-
vessel of operating power plants to provide accurate estimates
vide uncertainty estimates for reactor fluences with a higher
of the irradiation embrittlement of the base and weld metal in
degree of confidence.
the vessel. The benchmark procedure must not only prove that
1.2 This standard does not purport to address all of the
calculations give reasonable results but that their uncertainties
safety concerns, if any, associated with its use. It is the
are propagated with due regard to the sensitivities of the
responsibility of the user of this standard to establish appro-
different input parameters used in the transport calculations.
priate safety and health practices and determine the applica-
Benchmarking is achieved by building up data bases of
bility of regulatory limitations prior to use.
benchmark experiments which have different influences on
2. Referenced Documents uncertainty propagation. For example, fission spectra are the
2
fundamental data bases which control propagation of cross
2.1 ASTM Standards:
section uncertainties, while such physics-dosimetry experi-
E261 Practice for Determining Neutron Fluence, Fluence
ments as vessel wall mockups, where measurements are made
Rate, and Spectra by Radioactivation Techniques
within a simulated reactor vessel wall, control error propaga-
E262 Test Method for Determining Thermal Neutron Reac-
tion associated with geometrical and methods approximations
tion Rates and Thermal Neutron Fluence Rates by Radio-
in the transport calculations. This guide describes general
activation Techniques
procedures for using neutron fields with known characteristics
E706 Master Matrix for Light-Water Reactor Pressure Ves-
to corroborate the calculational methodology and nuclear data
sel Surveillance Standards, E 706(0)
used to derive neutron field information from measurements of
neutron sensor response.
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This test method is under the jurisdiction ofASTM Committee E10 on Nuclear
3.2 The bases for benchmark field referencing are usually
Technology and Applications and is the direct responsibility of Subcommittee
irradiations performed in standard neutron fields with well
E10.05 on Nuclear Radiation Metrology.
known energy spectra and intensities. There are, however, less
Current edition approved Jan. 1, 2005. Published February 2005. Originally
well known neutron fields that have been designed to mockup
approved in 1999. Last previous edition approved in 1999 as E2006 - 99. DOI:
10.1520/E2006-05.
special environments, such as pressure vessel mockups in
2
For referenced ASTM standards, visit the ASTM website,
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