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

Journal Article · Tue Jun 22 00:00:00 EDT 2010 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.4757173· OSTI ID:21410497

Perkasa, Yudha S ^[1]; Kurniadi, R; Basar, K; Waris, A ^[2]

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1. Department of Physics, Jl. Ganesa 10 Bandung 40132 (Indonesia)
2. Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa 10 Bandung 40132 (Indonesia)

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 .

• OSTI ID: 21410497
• Journal Information: AIP Conference Proceedings, Vol. 1244, Issue 1; Conference: ICANSE 2009: 2. international conference on advances in nuclear science and engineering 2009, Bandung (Indonesia), 3-4 Nov 2009; Other Information: DOI:; (c) 2010 American Institute of Physics; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALPHA PARTICLES
AMERICIUM 241
APPROXIMATIONS
COMPUTERIZED SIMULATION
CROSS SECTIONS
ENERGY-LEVEL DENSITY
EVALUATION
FERMI LEVEL
FISSION
FISSION BARRIER
FISSION YIELD
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
OPTICAL MODELS
PARITY
REACTION KINETICS
THORIUM 232
TRANSMISSION
URANIUM 235
WAVELENGTHS
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
AMERICIUM ISOTOPES
BARYON REACTIONS
CALCULATION METHODS
CHARGED PARTICLES
ENERGY
ENERGY LEVELS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HADRON REACTIONS
HEAVY NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
IONIZING RADIATIONS
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
KINETICS
MATHEMATICAL MODELS
MINUTES LIVING RADIOISOTOPES
NUCLEAR POTENTIAL
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
PARTICLE PROPERTIES
POTENTIAL ENERGY
POTENTIALS
RADIATIONS
RADIOISOTOPES
SIMULATION
SPONTANEOUS FISSION RADIOISOTOPES
THORIUM ISOTOPES
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
YIELDS