Program - Brookhaven National Laboratory

and MCNP and CONSYST/ABBN system. The current version of library of group constants ABBN is
based on evaluated nuclear data files ROSFOND2010.
Corresponding author: Anton Peregudov
1.A.A. Blyskavka, G.N. Manturov, M.N. Nikolaev, A.M. Tsiboulia. “Multigroup Monte Carlo Code MMK-
KENO,” Preprint IPPE-3145, Institute for Physics and Power Engineering, Obninsk (2009). (In Russian.)
2.“Multigroup Constant Set for Calculation of Neutron and Photon Radiation Fields and Functionals, Including
the CONSYST2 Program,” ORNL. RSICC DLC-182 (1995). 3.http://www-nds.iaea.org/exfor/endf.htm
PR 47
Nuclear Data Needs for the Neutronic Design of MYRRHA Fast Spectrum Research
Reactor
Alexey Stankovskiy, Gert Van den Eynde, Edouard Malambu, Wim Uyttenhove, Peter Baeten, Institute
of Advanced Nuclear Systems, SCK-CEN, Boeretang 200, B-2400 Mol, Belgium.
MYRRHA is the fast spectrum research reactor being developed at SCK-CEN, Belgium. It is supposed to
operate both in critical and sub-critical (coupled with the proton linear accelerator delivering 600 MeV, 3.5
mA proton beam) operation modes. This is a pool type facility cooled with lead-bismuth eutectic (LBE).
This LBE also serves as a spallation target for sub-critical operation mode. The facility is designed to
operate with mixed oxide fuel. The pre-licensing phase will end in 2014 and to that date, among other
tasks, the reference nuclear data (general and special purpose libraries) must be identified and validated.
The Belgian licensing authorities require that further neutronic design and support works on MYRRHA
must be performed with this selected, validated and approved data set. First step towards the creation and
validation of such data set is the nuclear data sensitivity and uncertainty analysis with respect to MYRRHA.
Using the covariance data available from recent generation general-purpose nuclear data libraries (JEFF-
3.1.2, ENDF/B-VII.1, JENDL-4.0, TENDL-2011) it has been identified that the uncertainties for certain
reaction types are underestimated and must be improved by setting up differential and integral experiments.
The priority list for the general-purpose nuclear data for MYRRHA includes fission, neutron capture and
(n,2n) cross-sections on Pu-238, Pu-239 neutron capture cross-section and fission neutron yields, fission
neutron yield of Pu-240, fission and elastic scattering cross-sections of Pu-241, Bi-209 neutron capture
and (n,2n) cross-sections, and Fe-56 neutron capture cross-section. The spallation target sub-assembly of
MYRRHA running in sub-critical mode is capable to host devices dedicated for material testing for fusion
research. It can provide high hydrogen- and helium-to-dpa ratios due to hard neutron spectrum (with the
presence of high-energy tail) and very high flux. This implies that the nuclear data on gas production and
radiation damage must be of high accuracy. The analysis of such data has been performed and uncertainties
have been identified. The burn-up calculations for MYRRHA require not only the high-quality reaction
cross sections but also the neutron-induced fission product yields represented as continuous energy data,
especially in the fast energy region, to properly calculate the reaction rates. The sensitivity analysis of
burn-up calculations to the prompt fission product yields has been performed and the problematic nuclides
have been identified.
PR 48
EASY-II(12) Renaissance: n, p, d, α, γ-induced Inventory Code System
Jean-Christophe Sublet, UK Atomic Energy Authority, Culham Science Centre, Abingdon OX14 3DB,
United Kingdom. James Eastwood and Guy Morgan, Culham Electromagnetics Ltd, Culham Science
Centre, OX14 3DB, United Kingdom.
287