COMPARISONS OF THE CALCULATIONS USING DIFFERENT CODES IMPLEMENTED IN MCNPX MONTE CARLO TRANSPORT CODE FOR ACCELERATOR DRIVEN SYSTEM TARGET
Küçük Resim Yok
Tarih
2012
Dergi Başlığı
Dergi ISSN
Cilt Başlığı
Yayıncı
Amer Nuclear Soc
Erişim Hakkı
info:eu-repo/semantics/closedAccess
Özet
The MCNPX code offers options based on physics packages; the Bertini, ISABEL, INCL4 intra-nuclear models, and Dresner, ABLA evaporation-fission models and CEM2k cascade-exciton model. The study analyzes the main quantities determining ADS performance such as neutron yield, neutron leakage spectra, and neutron and proton spectra in the target and in the beam window calculated by the MCNPX-2.5.0 Monte Carlo transport code, which is a combination of LAHET and MCNP codes. The results obtained by simulating different models, cited above and implemented in MCNPX are compared with each other. The investigated system is composed of a natural lead cylindrical target and stainless steel (HT9) beam window. Target has been optimized to produce maximum number of neutrons with a radius of 20 cm and 70 cm of height. Target is bombarded with a high intensity linear accelerator by a 1 GeV, 1 mA proton beam. The protons are assumed uniformly distributed across the beam of radius 3 cm, and entering the target through a hole of 5.3 cm radius. The proton beam has an outer radius of 5.3 cm and an inner radius 5.0 cm. The maximum of the neutron flux in the target is observed on the axis similar to 10 cm below the beam window, where the maximum difference between 7 different models is similar to 15 %. The total neutron leakage out of the of the target calculated with the Bertini/ABLA is 1.83x10(17) n/s, and is about 14 % higher than the value calculated by the INCL4/Dresner (1.60x10(17) n/s). Bertini/ABLA calculates top, bottom and side neutron leakage fractions as 20 %, 2.3 %, 77.6 % of the total leakage, respectively, whereas, they become 18.6 %, 2.3 %, 79.4 % with INCL4/Dresner combination.
Açıklama
15th International Conference on Emerging Nuclear Energy Systems -- MAY 15-19, 2011 -- San Francisco, CA
Anahtar Kelimeler
Intranuclear-Cascade Calculation, Nucleon-Nucleus Interactions, High-Energy
Kaynak
Fusion Science and Technology
WoS Q Değeri
Q3
Scopus Q Değeri
Q2
Cilt
61
Sayı
1T
