Nuclear Data Section
International Atomic Energy Agency
P.O.Box 100, A-1400 Vienna, Austria
Memo CP-D/699

Date:
To:
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18 May 2011
Distribution
V. Semkova, N. Otsuka

Subject:

Compilation of experimental data for standard cross sections
evaluation

Neutron cross section standards are important for measurements and evaluations ofneutron cross sections. They are regularly re-evaluated. Last re-evaluation wascompleted at 2006. It was based at the GMA database of the results of measurements
assembled by Wolfgang Poenitz (W.P. Poenitz, S.E. Aumeier, Report ANL/NDM139 (1997)) updated with new results available to 2004. It includes the data
available from the EXFOR database, the literature, or obtained as private
communications from the authors. Comprehensive information regarding the last
neutron cross-section standard evaluation is available at: http://wwwnds.iaea.org/standards/.
We considered important that EXFOR database should
contain information for all standard cross section measurements. But this is not a caseat present. A list of data (and corresponding articles) included in the GMA database
but still has not been compiled in EXFOR was prepared. The table below contains thereferences with indication of the Data Centres responsible for the compilation. NDS
can provide pdf copy for some of the articles.
Numerical data used in the standard evaluation are given in the text file at
http://www-nds.iaea.org/standards/LastResults/GMDATA-21Oct04.CRD

in input format for GMA data preparation code DATA. Description of the format isgiven in the ANL/NDM-139 report (http://www-nds.iaea.org/standards/Reports/ANLNDM-139.pdf). Vladimir Pronyaev (Pronyaev@ippe.ru) may help in case of problems ofunderstanding of format. Because the data had not been received from authors
directly, compilers should indicate the source of data under STATUS. (Below a new
STATUS code PENTZ is introduced). The attention should be paid, that GMA uses
so-called “primary measured quantities” (e.g. ratio of cross sections if measurement
was done relative other reaction) in the evaluation, which often are not last result
presented by the authors (e.g. absolute cross section). Also, the components ofuncertainties needed for generation of covariances matrices of uncertainties ofexperimental data in cases when they are not given by the authors can be assigned on
the basis of the experts’ estimation.

ExampleSTATUS (PENTZ) Data extracted from W.P. Poenitz’s data collection (ANL/NDM139).

Reference

1Renner, C. (1978) PhD thesis, Universidade de São Paulo,Brazil.

2

J.R. Lemley, G.A. Keyworth, and B.C. Diven, “High
Resolution Fission Cross Section of Uranium-235 from 20 to
100 keV”, Nucl. Sci. Eng. 43, 281-285 (1971).

3

F. Corvi, (1983) personal communication, 235U(n,f)/6Li(n,α).

4W.P. Poenitz, BNL-NCS-51388.

5W.P.
Poenitz
andJ.W.
unpublished, 6Li(n,a)/235U(n,f).

6C. Wagemans, G. Coddens, H. Weigmann, R. Barthelemy,“Measurement of the 239Pu(n,f) cross section from thermal
up to 30 keV neutron energy”. Annals of Nuclear Energy, 7(9), 495,1980.

7J.F. Barry, “Cross Section for the Reaction 6Li(n,α)t”, inProceedings of a Conference on “Neutron Cross Section
Technology”, Washington, D. C., March 22-24, 1966, p. 763.

8W.P. Poenitz, J.W. Meadows, “The 6Li(n,a) Cross-Section”
in the Proceedings of a Panel Neutron Standard Reference
Data, Vienna, 20-24 November 1972, p. 95, IAEA, Vienna,
1974, STI/PUB/371, ISBN 92-0-031074-5.
W.P. Poenitz, “Relative and Absolute Measurements of theFast-Neutron Fission Cross-Section of Uranium-235”, Nucl.
Sci. Eng. 53, 370-392 (1974).

9Meadows,(1976)

10

R.L. Macklin, “Gold Neutron Capture Cross Section from100 to 2000 keV”, Nucl. Sci. Eng. 79, 265-268 (1981).

11

R.L. Macklin, J. Halperin, R.R Winters, “Gold neutroncapture cross section from 3 to 550 keV”, Phys. Rev. C
11, C1270, 1975.

12H, Condé, S. Schwarz and N. Starfelt, A method for theCentre(# indicates data set
number in GMDATA21Oct04.CRD)
NDS
Missing in EXFOR:
LI6(N,A) (#202)
NNDC
Missing in EXFOR:
U5(N,F)/LI6(N,A) (#244)
NEA DB
Missing in EXFOR:
U5(N,F)/LI(N,A) (#531)
NNDC
Missing in EXFOR:
LI6(N,A) (#702)
NNDC
Missing in EXFOR:
6LI6(N,A)/U5(N,F)(#250)NEA DB(EXFOR 21704)
Missing in EXFOR:
PU9(N,F)/LI6(N,A)(#547)NEA DB(EXFOR 20893)
Missing in EXFOR:
LI6(N,A)/U5(N,F) (#288)
NNDC
Missing in EXFOR:
LI6(N,A) (#241)
NNDC(EXFOR 10333)
Missing in EXFOR:
U5(N,F)/LI6(N,A) (#561)
NNDC(EXFOR 12720)
Missing in EXFOR:
AU(N,G)/LI6(N,A) (#313)
AU(N,G)/U5(N,F) (#314)
NNDC(EXFOR 10432)
Missing in EXFOR:
197Au(n,g)/6Li(n,a)(#312)NEA DBabsolute measurements of fast neutron flux with a large
liquid scintillator”, Arkiv för fysik 29, 45, 1965.

(EXFOR 20112)
Missing in EXFOR:
LI6(N,A) (#198)
CJD(EXFOR 41272)
Missing in EXFOR.
LI6(N,A)/B(N,A) (#160)

13

A.A Bergman, A.I. Isakov, IU. P. Popov, and F.L. Shapiro,“MEASUREMENTS WITH THE SLOWING-DOWNTIME NEUTRON SPECTROMETER EMPLOYINGLEAD. EXCITED LEVEL OF THE He4 NUCLEUS”, (1957) Zh. Eksp. Teor. Fiz. 33, 9; English translation inSoviet Physics - JETP 6, 6,1958

14

H.G. Silk, B.O. Wade, Harwell Report, AERE-M 2366(1970)NEA DB

15J.W. Meadows, in the Proceedings of a Symposium on
Neutron Standards and Flux Normalization, 129 (1971)

16W. Becker, A.J. Deruytter, J. Wartena, in the Proceedings ofa Symposium on Neutron Standards and Flux Normalization,125 (1971)

NNDC
Missing in EXFOR.
LI6(N,A) (#707)
NNDC

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