The Fifth Conference “ Nuclear Science and Its Application”, 14-17 October 2008
CALCULATION OF NEUTRON-INDUCED FISSION CROSS SECTIONS
FOR 231 233 PA AND 234-238U ISOTOPES UP TO 20 MEV.
M. GÜNAY2, M. E. KORKMAZ1. M. YİĞİT1, B. ŞARER1
1 Gazi Üniversitesi, Fen-Edebiyat Fakültesi, Fizik Bölümü, 06500 Ankara-Turkey 2înönü Üniversitesi, Fen-Edebiyat Fakültesi, Fizik Bölümü, M alatya-Turkey E-mail: mkorkmaz@gazi.edu.tr
Neutron fission cross sections for the isotopes 231233 Pa and 234-238U have been calculated. In the calculations two program codes, ALICE/ASH and CEM03.01, were used. The results have been compared with the experimental values and some evaluated data files.
Neutron induced reaction cross sections in the energy range up to 20 MeV are required for several applications of nuclear technology. Nuclear cross section data can be obtained by three different ways on the basis of experimental measurement, theoretical model calculations, and evaluation datafiles.
The code ALICE was originated by Blann. ALICE/ASH is, added additional physics, capabilities and corrections, a modified version of the ALICE code. Intranuclear transition rates were calculated using the effective cross section of nucleon-nucleon interactions in nuclear matter. Corrections were made to the GDH approach for the treatment o f effects in peripheral nuclear regions.
The CEM03.01 is an extended and improved version o f the earlier code CEM2k+CEM2, which implement versions of the Cascade-Exciton Model (CEM) o f nuclear reactions.
