Evaluation of Integral Quantities in an Accelerator Driven System Using Different Nuclear Models Implemented in the Mcnpx Monte Carlo Transport Code

dc.authorid celik, yurdunaz/0000-0002-9211-8510
dc.authorscopusid 14027391200
dc.authorscopusid 7102942712
dc.authorscopusid 54384850100
dc.authorscopusid 23667264200
dc.authorwosid Sarer, Basar/B-9445-2015
dc.authorwosid DÜZ, Mehtap/AAS-3672-2020
dc.authorwosid Şahin, Sŭmer/C-6252-2013
dc.contributor.author Sarer, Basar
dc.contributor.author Sahin, Sumer
dc.contributor.author Celik, Yurdunaz
dc.contributor.author Gunay, Mehtap
dc.contributor.other Department of Mechanical Engineering
dc.date.accessioned 2024-07-05T14:26:09Z
dc.date.available 2024-07-05T14:26:09Z
dc.date.issued 2013
dc.department Atılım University en_US
dc.department-temp [Sarer, Basar] Gazi Univ, Fac Sci, TR-06503 Ankara, Turkey; [Sahin, Sumer] Atilim Univ, Fac Engn, TR-06836 Ankara, Turkey; [Celik, Yurdunaz] Gazi Univ, Inst Sci & Technol, TR-06503 Ankara, Turkey; [Gunay, Mehtap] Inonu Univ, Fac Sci & Arts, TR-44280 Malatya, Turkey en_US
dc.description celik, yurdunaz/0000-0002-9211-8510 en_US
dc.description.abstract 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. This study analyzes the main quantities determining ADS performance, such as neutron yield, neutron leakage spectra, heating 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. The target has been optimized to produce maximum number of neutrons with a radius of 20 cm and 70 cm of height. The 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 53 cm and an inner radius of 5.0 cm. The maximum value 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 of the target calculated with the Bertini/ABLA is 1.83 x 10(17) n/s, and is about 14% higher than the value calculated by the INCL4/Dresner (1.60 x 10(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, the calculated fractions are 18.6%, 2.3%, 79.4%, respectively, with INCL4/Dresner combination. The largest heat deposition density by considering all particles in the beam window calculated with CEM2k model is 104 W/cm(3)/mA, which is 9.0% greater than the lowest value predicted with INCL4/Dresner model (95.4 W/cm(3)/mA). The maximum average heat deposition density for all particles in the target is calculated as 6.87 W/cm(3)/mA with INCL4/ABLA. (C) 2013 Elsevier Ltd. All rights reserved. en_US
dc.identifier.citationcount 7
dc.identifier.doi 10.1016/j.anucene.2013.05.045
dc.identifier.endpage 389 en_US
dc.identifier.issn 0306-4549
dc.identifier.scopus 2-s2.0-84881101855
dc.identifier.startpage 382 en_US
dc.identifier.uri https://doi.org/10.1016/j.anucene.2013.05.045
dc.identifier.uri https://hdl.handle.net/20.500.14411/109
dc.identifier.volume 62 en_US
dc.identifier.wos WOS:000327170800045
dc.identifier.wosquality Q2
dc.institutionauthor Şahin, Sümer
dc.language.iso en en_US
dc.publisher Pergamon-elsevier Science Ltd en_US
dc.relation.publicationcategory Makale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanı en_US
dc.rights info:eu-repo/semantics/closedAccess en_US
dc.scopus.citedbyCount 10
dc.subject Accelerator driven systems en_US
dc.subject Monte Carlo methods en_US
dc.subject Lead target en_US
dc.subject Proton beams en_US
dc.subject Nuclear models en_US
dc.subject Neutron spectra en_US
dc.title Evaluation of Integral Quantities in an Accelerator Driven System Using Different Nuclear Models Implemented in the Mcnpx Monte Carlo Transport Code en_US
dc.type Article en_US
dc.wos.citedbyCount 7
dspace.entity.type Publication
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