Program - Brookhaven National Laboratory

and applications using statistical and systematic uncertainties and experimental covariance matrices are
provided with computational data in C5, C5M format. Additionally they can construct correlation matrices
using interactive Web tool. Web without Internet. This project implements complete standalone
Web database retrieval system on USB memory stick or USB disk. It can include also various nuclear
data applications. Allows to use Web EXFOR/CINDA/ENDF database retrieval systems locally without
Internet. The package does not need any installation procedures. Web-Tools for compilers, evaluators
and experimentalists provides server calculations, running utility codes and comparison users’ data with
central databases. A system integrating information from EXFOR, CINDA and NSR databases provides
Web search helping to extend EXFOR database by missing data.
[1] V.V. Zerkin, V. McLane, M.W. Herman and C.L. Dunford, presented at International Conference on
Nuclear Data for Science and Technology, 27 September - 1 October 2004, Santa Fe, USA; also published
in AIP Conf. Proc. - Int. Conf. on Nuclear Data for Science and Technology, Vol. 769, Part 1 (2005)
pp. 586-589, AIP, Melville, New York, ISBN 0-7354-0254-X, ISSN 0094-243X. [2] V. Zerkin, A. Trkov,
in Proceedings of the International Conference on Nuclear Data for Science and Technology, April 22-27,
2007, Nice, France, EDP Sciences, 2008, pp. 769-772.
PR 18
Calculation of Delayed Neutron Yields for Various Libraries
Tan Dat Huynh, CEA Saclay, DEN/DANS/DM2S/SERMA/LLPR, 91191 Gif sur Yvette Cedex,
FRANCE.
This paper presents the comparison between the calculated delayed neutron yields and the recommended
values proposed by Tuttle [1], the experimental data of Waldo [2] and those of Benedetti [3]. These data
are given for thermal, fast, and high energy fission ranges. The calculation of total delayed neutron yields
is performed either by the NJOY [4] nuclear data processing system or by the summation method [5].
In the NJOY calculation, the data used come from the general purpose evaluation files. The delayed
neutron yields were calculated in thermal and fast energy groups using the weighting function composed
of maxwellian, 1/E and fission spectrum. In the summation calculation, the data used are the delayed
neutron branching ratios (also called delayed neutron emission probabilities) and the cumulative fission
yields which are given for thermal, fast, high energy fission and spontaneous fission. These data are found
in the Radioactive Decay Data and Fission Yield Data files (File 8) of nuclear data evaluations. The NJOY
and the summation calculation were carried out with various libraries such as JEF-2, JEFF-3, ENDF/B-VI
and ENDF/B-VII. The accuracy of the comparisons allow the validation of the data used in these libraries.
This work is carried out in the frame of the expertise activity of the GALILEE project [6].
[1] Tuttle R. J., Report INDC NDS - 107/G + special, p. 29-67, IAEA, Vienna 1979. [2] Waldo R. W.,
Karam R. A. & Meyer R. A., Physical Review C, Vol. 23, n 3, March 1981. [3] Benedetti G., Cesana A.,
Sangiust V. & Terrani M., Nuclear Science and Engineering : 80, p. 379-387, 1982. [4] MacFarlane R. E.
et al, LA-UR 89-2057, LANL, USA, 1994. [5] Liaw J.R. and England T.R., Trans. Amer. Nucl. Soc. 28,
750 (1978). [6] Coste-Delclaux M., “GALILEE : A nuclear data processing system for transport, depletion
and shielding codes”, International Conference on the Physics of Reactors “Nuclear Power : A sustainable
Resource”, Casino-Kursaal Conference Center, Interlaken, Switzerland, (2008).
PR 19
A TOF Spectrometer for β-delayed Neutron Emission Measurements
270