COMPARISONS OF THE CALCULATIONS USING DIFFERENT CODES IMPLEMENTED IN MCNPX MONTE CARLO TRANSPORT CODE FOR ACCELERATOR DRIVEN SYSTEM TARGET

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dc.authoridcelik, yurdunaz/0000-0002-9211-8510
dc.authorwosidDÜZ, Mehtap/AAS-3672-2020
dc.authorwosidŞahin, S?mer/C-6252-2013
dc.contributor.authorSarer, Basar
dc.contributor.authorSahin, Sumer
dc.contributor.authorGunay, Mehtap
dc.contributor.authorCelik, Yurdunaz
dc.date.accessioned2024-08-04T20:35:46Z
dc.date.available2024-08-04T20:35:46Z
dc.date.issued2012
dc.departmentİnönü Üniversitesien_US
dc.description15th International Conference on Emerging Nuclear Energy Systems -- MAY 15-19, 2011 -- San Francisco, CAen_US
dc.description.abstractThe 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.en_US
dc.identifier.doi10.13182/FST12-A13437
dc.identifier.endpage307en_US
dc.identifier.issn1536-1055
dc.identifier.issn1943-7641
dc.identifier.issue1Ten_US
dc.identifier.scopus2-s2.0-84857563806en_US
dc.identifier.scopusqualityQ2en_US
dc.identifier.startpage302en_US
dc.identifier.urihttps://doi.org/10.13182/FST12-A13437
dc.identifier.urihttps://hdl.handle.net/11616/95581
dc.identifier.volume61en_US
dc.identifier.wosWOS:000299608100051en_US
dc.identifier.wosqualityQ3en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherAmer Nuclear Socen_US
dc.relation.ispartofFusion Science and Technologyen_US
dc.relation.publicationcategoryKonferans Öğesi - Uluslararası - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectIntranuclear-Cascade Calculationen_US
dc.subjectNucleon-Nucleus Interactionsen_US
dc.subjectHigh-Energyen_US
dc.titleCOMPARISONS OF THE CALCULATIONS USING DIFFERENT CODES IMPLEMENTED IN MCNPX MONTE CARLO TRANSPORT CODE FOR ACCELERATOR DRIVEN SYSTEM TARGETen_US
dc.typeConference Objecten_US

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