Engineering topics

Perkasa, Yudha S

Publications and source records attributed to Perkasa, Yudha S.

3 records

DOE OSTI2012

Neck curve polynomials in neck rupture model

The Neck Rupture Model is a model that explains the scission process which has smallest radius in liquid drop at certain position. Old fashion of rupture position is determined randomly so that has been called as Random Neck Rupture Model (RNRM). The neck curve polynomials have been employed in the Neck Rupture Model for calculation the fission yield of neutron induced fission reaction of {sup 280}X{sub 90} with changing of order of polynomials as well as temperature. The neck curve polynomials approximation shows the important effects in shaping of fission yield curve.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2010

Fission Cross Section and Fission Yield Calculation of Am-241 (n,f), Th-232 (n,f), and U-235 (n,f) using TALYS

Nuclear data evaluation for fission cross section and fission yield had been performed by many investigators using different model approximation theoretically. These models are encapsulated and implemented into computer codes to perform more robust nuclear reaction data calculations. TALYS is one of most successful nuclear reaction codes that used to determine fission cross section and fission yield. In this paper, TALYS was used to calculate some fission reaction including Am-241 (n,f), Th-232 (n,f), and U-235 (n,f). These calculations are performed using different set of reaction mechanism and optical model parameter adjustment, such as fission barrier parameter, level density parameter, transmission mechanism, and so on. Reaction mechanism and parameter adjustment are selected based on reaction characteristics to obtain more accurate and reasonable result. The accuracy of calculation result are heavily depends on the reaction mechanism selection and parameter adjustment. All obtained result will be compared with ENDF nuclear data library. This work implemented as preliminary study for calculation of fission cross section using modified method of level density parameter determination. Further work will be more focused to the primary target, that is calculation of any fission cross section using different level density models where its level density parameter (LDP) is approximated by Thermal wavelength instead of RIPL data .

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2010

Fission Cross Section Calculation Using TALYS Based on Two Different Level Density Models

Fission cross sections in statistical model of fission are calculated using one of important parameter such as transmission coefficients. This parameter calculated using optical model parameter and level density. There are several models of level density that can be used to predict fission cross section. They are Constant Temperature Model, Fermi Gas Model, Back-Shifted Fermi Gas Model, and Generalized Superfluid Model. In this work, fission cross section would be calculated using two different model of level density, such as Constant Temperature Model Plus Fermi Gas and Generalized Superfluid Model on Th-232 (n,f) fission reaction. Calculation result from two different model then would be compared with experimental data from ENDF B/VI. Analysis of result would lead to the conclusion of spesific characteristic for each model in every fission cases. This work has became a preliminary study to calculate fission cross section using different set of level density models. Further work will be implemented to calculate similar fission cross section using level density parameter that approximated by Thermal wavelength [see 21].

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗