Program - Brookhaven National Laboratory

The Russian Nuclear Data Library for Radiation Damage and Transmutation Study of
Irradiated Materials
A.I. Blokhin, N.A. Demin, V.N. Manokhin, I.V. Sipachev, A.I.Leypunsky Institute of Physics and Power
Engineering, Bondarenko sq., 1, 249033 Obninsk, Russia. D.A. Blokhin, V.M. Chernov, A.A. Bochvar
Institute of Non-Organic Materials, Rogova str.5, 123060 Moscow, Russia.
General requirements in nuclear data for calculations of activation, transmutation and radiation damage
in fission and fusion reactor materials are formulated in many works and reported at the IAEA special
meetings. These requirements take into account the nuclear data for main structural materials and for
their alloys and reaction products. The list of neutron reactions important for fission and fusion power
plant technology was prepared. To meet the nuclear data needs the several large neutron data libraries
were created, mainly by theoretical calculations. On the base of national and regional data libraries
the new data library ACDAM [1] for activation/damage calculations in structural reactor materials was
created. The library ACDAM consists from three parts: Activation/transmutation neutron cross-section
base - contains evaluated neutron induced reaction cross-sections at the energies 0 - 20 MeV for 704 stable
and unstable nuclei from H-1 to Po-210; Decay Data Library (DeDaL) - is created for 1100 radioactive
nuclei from H-1 to Cf-252; Damage Data Library (DDL) - contains the displacement cross sections for
nuclei H, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C, N, O, F, Na-23, Mg, Al, Si, P, S, Cl, K, Ca, Ti,
V, V-51, V-50, Cr, Cr-50,52,53,54, Mn-55, Fe, Fe-54,56,57,58, Co-59, Ni, Ni-58,59,60,61,62,64, Cu-63,65,
Zr, Zr-90,91,92,94,96, Nb-93, Mo, Ag, Ag-107,109, Ta-181, W-182,183,184,186, Pt, Au and is based on
processing of the general purpose data files from the BROND-3, ENDF/B-VII.1 and JENDL-4.0 libraries.
The report describes the results of comparison and analysis of available experimental data and evaluated
cross sections and predictions of systematic received in the Russian Nuclear Data Center (SSC RF IPPE).
The recommendations are given for selection of reliable nuclear data and improving their quality. The
current new data library ACDAM allows to estimate many activation/radiation damage characteristics of
structural materials and alloys for any type of neutron fission/fusion spectra in neutron energy range up
to 20 MeV.
[1] A.I. Blokhin, N.A. Demin, V.N. Manokhin, I.V. Sipachev, D.A. Blokhin, and V.M. Chernov. Software
Package ACDAM for Investigation of Nuclear Physical Properties of Materials in Conditions of Long-Term
Neutron Irradiation. Inorganic Materials: Applied Research, 2010, Vol. 1, No. 4, pp. 311-319
PR 39
Effect of New Cross Section Evaluations on Calculated Flux in Irradiation Positions of
Egypt Second Research Reactor
Mohamed A. Elsaied, Mohamed A. Gaheen, Egypt Second Research Reactor (ETRR-2), Egyptian Atomic
Energy Authority (EAEA), Egypt.. Esmat H. Amine, Nuclear and Radiological Regulatory Authority
(NRRA), Egypt.
The objective of this paper is to study the effect of new cross section libraries which produced by IAEA
nuclear data libraries updated in WLUP (WIMS Libraries Updates Project) on calculated flux in irradiation
positions of Egypt second Research Reactor (ETRR-2). Standard computer codes such as a transport
theory lattice simulation code WIMS-5B and diffusion theory based global core calculations computer
code CITVAP v3.1 (new version of CITATION II developed by INVAP) were used to perform this study.
For the proposed calculations, the following libraries have been used: WIMSD4 (69 energy groups), IAEA
(69 energy groups), IAEA (172 energy groups). Evaluation of the 3D flux distribution in irradiation
positions using CITVAP v3.1 code and macroscopic cross-section libraries generated using WIMS-5B is
compared with experimental results. This work was supported by IAEA under some contract with EAEA.
282