Program - Brookhaven National Laboratory

PR 84
ANDES Measurements for Advanced Reactor Systems
A. Plompen, F.-J. Hambsch, S. Kopecky, M. Nyman, C. Rouki, P. Salvador Casti¨neira, P. Schillebeeckx,
EC-JRC-IRMM, 2440 Geel, Belgium. F. Belloni, E. Berthoumieux, F. Gunsing, C. Lampoudis, CEA,
Saclay, France. M. Calviani, C. Guerrero, CERN, Geneva, Switzerland. D. Cano Ott, E. Gonzalez
Romero, CIEMAT, Madrid, Spain. M. Aïche, B. Jurado, L. Mathieu, CNRS/IN2P3/CENBG,
Bordeaux-Gradignan, France. X. Derckx, F. Farget, C. Rodriguez Tajes, CNRS/IN2P3/GANIL, Caen,
France. A. Bacquias, Ph. Dessagne, M. Kerveno, CNRS/IN2P3/IPHC, Strasbourg, France. C. Borcea, A.
Negret, IFIN-HH, Bucharest-Magurele, Romania. N. Colonna, INFN, Bari, Italy. I. Goncalves, ITN,
Lisbon, Portugal. H. Penttilä, S. Rinta-Antila, V.S.Kolhinen, A. Jokinen, Jyväskylä University,
Jyväskylä, Finland.
Advanced reactor systems are of interest to minimizing high level waste and maximizing utilization of
resources while implementing the highest standards of safety and security. Recent sensitivity studies
demonstrate the need for very tight nuclear data uncertainties to enable reliable and accurate estimates of
key reactor and fuel cycle parameters. Such needs were prioritized and are advertised by the OECD Nuclear
Energy Agency. Many of these needs require a combination of accurate measurements and dedicated
new nuclear data evaluations to take optimal advantage of this new work. A significant number of new
measurements was undertaken by the ANDES ”Measurements for advanced reactor systems” initiative.
ANDES (Accurate Nuclear Data for nuclear Energy Sustainability) is an integrated project co-sponsored by
the seventh framework programme (FP7) of the European Commission. These new measurements include
neutron inelastic scattering off 238 U, 23 Na, Mo, and Zr, neutron capture cross sections of 238 U, 241 Am,
neutron-induced fission cross sections of 240 Pu, 242 Pu, 241 Am, 243 Am and 245 Cm, and measurements that
explore the limits of the surrogate technique. The latter study the feasibility of inferring neutron capture
cross sections for Cm isotopes, the neutron-induced fission cross section of 238 Pu and fission yields and
fission probabilities through full Z and A identification in inverse kinematics for isotopes of Pu, Am,
Cm and Cf. Finally, four isotopes are studied which are important to improve predictions for delayed
neutron precursors and decay heat by total absorption gamma-ray spectrometry ( 88 Br, 94 Rb, 95 Rb, 137 I).
The measurements which are performed at state-of-the-art European facilities (CENBG, CERN n TOF,
GANIL, IRMM, Jyväskylä University, Oslo Cyclotron Laboratory) have the ambition to achieve the lowest
possible uncertainty, and to come as close as is reasonably achievable to the target uncertainties established
by the above mentioned sensitivity studies. An overview will be presented of the activities and achievements
of this initiative leaving detailed expositions to the various parties contributing to the conference.
PR 85
Neutron Inelastic Scattering Measurements for Na, Cu, Mo, Zr, Ge, Th and U
A. Plompen, C. Rouki, M. Nyman, N. Nankov, EC-JRC-IRMM, 2440 Geel, Belgium. Ph. Dessagne, M.
Kerveno, A. Bacquias, J.C. Thiry, H. Karam, CNRS/IN2P3/IPHC, Strasbourg, France. C. Borcea, A.
Negret, IFIN-HH, Bucharest-Magurele, Romania. S. Goriely, ULB, Brussel, Belgium. S. Hilaire, P.
Romain, CEA/DAM, Arpajon, France. P. Archier, C. De Saint Jean, G. Nogure, C. Vaglio-Gaudard,
CEA/DEN, Cadarache, France. A. Koning, NRG, Petten, The Netherlands. A. Domula, K. Zuber, TU
Dresden, Dresden, Germany. L. Leal, ORNL, Oak Ridge, USA.
Studies for advanced reactor systems such as sodium-cooled fast reactors designed for recycling of high
level waste, accelerator driven systems for transmutation, and systems envisioning the use of the Th/U
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