Program - Brookhaven National Laboratory

1994 core and the 2010 core, we calculated the criticality, isothermal temperature coefficient, the effective
delayed neutron fraction, etc, as well as the associated uncertainties. The goal of the work is to evaluate the
performance of unadjusted, best-estimate nuclear data evaluations for fast reactor applications. Present
study includes the FY2011 results of the “Core R & D program for the commercialization of the fast
breeder reactor by utilizing Monju”, entrusted to the University of Fukui by the Ministry of Education,
Culture, Sports and Technology of Japan (MEXT)
Corresponding author: Naoki Yamano
[1] P. Tamagno and W.F.G. van Rooijen, “Uncertainty Analysis of the prototype FBR Monju with the
JENDL-4.0 nuclear data set”, accepted for publication in Annals of Nuclear Energy (2012).
PE 3 4:20 PM
Impact on Advanced Fuel Cycle and its Irradiated Fuel due to Nuclear Data Uncertainties
and Comparison Between Libraries
C.J. Diez, O. Cabellos, J.S. Martinez
Universidad Politécnica de Madrid (UPM), José Gutiérrez Abascal 2, 28006, Madrid, Spain
An adequate determination of safety and economical margins of nuclear systems relies directly on the
uncertainties of nuclear data. One of the ANDES project objectives is to enhance the European capability
to produce covariance data for isotopes which are important for advanced reactors, as identified from recent
sensitivity studies on GEN-IV reactors and ADS. Thus, the new covariance data for nuclear reactions,
radioactive decay and fission yields will be processed and used in reactor/fuel cycle codes to calculate their
impact on advanced reactor and fuel cycle parameters such as EFIT. Different nuclear data libraries and
sources of uncertainty will be compared, and also new fission yields covariance data generated under the
framework of ANDES project will be propagated and compared with other covariance data. The impact of
the fission product nuclear data uncertainties on the inventory of the irradiated fuel will be analysed. Thus,
a complete study of the importance of nuclear data uncertainties on advanced fuel cycle and inventory of
irradiated fuel will be performed by using the ACAB code, which includes all the capabilities for nuclear
data uncertainty propagation by a Monte Carlo approach. The research leading to these results has received
funding from the European Atomic Energy Community’s Seventh Framework Programme [FP7/2007-2013]
under grant agreement n 249671, (FP7-EURATOM-FISSION-2009:Project ANDES/249671). Also, it has
been partially supported by ”Ministerio de Educación (Ministry of Education)” of Spain through the FPU
Program for teaching and researching formation (Programa de Formación de Profesorado Universitario)
under grant AP2009-1801 for the first author.
PE 4 4:40 PM
Sensitivity of the Shielding Benchmarks on Variance-Covariance Data for Scattering
Angular Distributions
C. Jouanne
CEA Saclay (France)
The nuclear data libraries for neutron interactions recently made available (ENDF/B-VII.1 [1], JENDL-
4.0 [2], JEFF-3.1.1 [3]) contain more and more variance-covariance data. These data focus on resonance
parameters and cross sections reactions. However, for some nuclei, variance-covariance data on scattering
anisotropy distributions are available. In this context, the TENDL-2011 [4] library is an exception because
it contains uncertainties for all the nuclei. Furthermore, this library provides a set of 31 evaluations for
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