Program - Brookhaven National Laboratory

with a central cavity where small size samples can be irradiated. Several integral experiments have been
carried out in the past or more recently on these facilities: fission yields evaluation of several actinides [1],
reactivity worth measurements by the perturbation method for fissile isotopes or non fissile elements [2]...
Accurate descriptions and models of the reactors, and particularly a CALIBAN benchmark published in
the ICSBEP handbook [3], are available and allow sharp analyses of these experiments. However, to improve
even further theses analyses, a higher knowledge of the neutron spectrums provided by the reactor
is needed. That is why studies to characterize theses spectrums have been performed for many years and
are still under progress. Several unfolding methods, based on activation foils measurements, have been
recently developed and applied to characterize CALIBAN and PROSPERO neutron spectrums [4-5]: iterative
perturbations, maximum entropy, Bayesian calibration, etc. In this article will be given a description
of the CALIBAN and PROSPERO reactors and a short presentation of the integral experiments recently
carried out on theses facilities. Then, unfolding methods used to characterize reactors neutron spectrums
will be presented. Finally, results will be discussed and compared.
[1] P. Casoli et al, Measurements of Actinide-Fission Product Yields in Caliban and Prospero Metallic
Core Reactor Fission-Neutron Fields, Journal of ASTM International, Vol. 9, No. 4, Paper ID JAI104018,
2012. [2] B. Richard, Reactivity Worth Measurements on Fast Burst reactor CALIBAN - Description and
Interpretation of Integral Experiments for the Validation of Nuclear Data, Proceedings of PHYSOR 2012,
Knoxville (TN), USA, April 15-20, 2012. [3] N. Authier et al, Bare Highly Enriched Uranium Fast Burst
Reactor CALIBAN, HEU-MET-FAST-080, International Handbook of Evaluated Criticality Safety Benchmark
Experiments, NEA Nuclear Science Committee, 2007. [4] X. Jacquet et al, New Measurements and
the Associated Unfolding Methodologies to Characterize the Caliban Pulsed Reactor Cavity Neutron Spectrum
by the Foil Activation Method, Journal of ASTM International, Vol. 9, No. 3, Paper ID JAI104020,
2012. [5] J. Cartier et al, Bayesian Calibration of Reactor Cavity Neutron spectrum, to be published in
the proceedings of M&C 2013, May 05-09, 2013.
CE 4 2:40 PM
Accurate Nuclear Data For Sustainable Nuclear Energy from the ANDES Project
Enrique M. Gonzalez-Romero
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, CIEMAT. Madrid (Spain), on
behalf of the ANDES Euratom project.
The ANDES FP7-EURATOM project, Accurate Nuclear Data for nuclear Energy sustainability, intends
to address the nuclear data needs associated to the new reactors and new fuel cycles supported by SNETP,
in its strategic research agenda and in the ESNII proposal, taking into account the priority lists for nuclear
data from NEA/OECD, FP6-EURATOM projects EUROTRANS-NUDATRA and CANDIDE. ANDES
combines a reduced group of selected differential measurements, the improvement in uncertainties and
covariance’s within the evaluation process and the validation of present and new data libraries using
integral experiments, to bring most critical nuclear data to the level of accuracies required by the new
reactors and system promoted by ESNII and the SNETP. In addition, a specific work package will improve
the prediction capabilities of high-energy transport codes for the design of ADS, developing better models
and performing a few selected measurements. The research of ANDES is particularly relevant for P & T
and other sustainability components of the fuel cycle because the involvement of isotopes, materials and
concepts not widely included in present reactors and often lacking of required accuracy and operational
experience. The progress and preliminary results of the project will be presented in this paper, including:
• Accurate new measurements of capture and other cross sections for minor actinides like 241 Am,
major actinides like 238 U, fission cross sections of Pu and minor actinides, and for other inelastic
cross sections,
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