Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors.
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| Title: | Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors. |
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| Authors: | Tran Minh, Tien1 (AUTHOR), Tran Quoc, Dung2 (AUTHOR) |
| Source: | Science & Technology of Nuclear Installations. 12/20/2021, Vol. 2021, p1-6. 6p. |
| Subjects: | Accelerator-driven systems, Nuclear reactors, Neutrons, Proton beams, Neutron flux, Research reactors |
| Abstract: | In this paper, the accelerator-driven subcritical reactor (ADSR) is simulated based on structure of the TRIGA-Mark II reactor. A proton beam is accelerated and interacts on the lead target. Two cases of using lead are considered here: firstly, solid lead is referred to as spallation neutron target and water as the coolant; secondly, molten lead is considered both as a target and as a coolant. The proton beam in the energy range from 115 MeV to 2000 MeV interacts with the lead to create neutrons. The neutron parameters as neutron yield Yn/p, neutron multiplication factor k, the radial and axial distributions of the neutron flux in the core have been calculated by using MCNPX program. The results show that the neutron yield increases as the energies of the proton beam increases. When using the lead target, the differences between the neutron yield are from 4.2% to 14.2% depending on the energies of the proton beam. The proportion of uranium in the mixtures should be around 24% to produce an effective neutron multiplier factor greater than 0.9. The neutron fluxes are much higher than the same calculations for the TRIGA-Mark II reactor model using tungsten target and light water coolant. [ABSTRACT FROM AUTHOR] |
| Copyright of Science & Technology of Nuclear Installations is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.) | |
| Database: | Engineering Source |
| FullText | Links: – Type: pdflink Text: Availability: 0 |
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| Header | DbId: egs DbLabel: Engineering Source An: 154481977 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Tran+Minh%2C+Tien%22">Tran Minh, Tien</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Tran+Quoc%2C+Dung%22">Tran Quoc, Dung</searchLink><relatesTo>2</relatesTo> (AUTHOR) – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Science+%26+Technology+of+Nuclear+Installations%22">Science & Technology of Nuclear Installations</searchLink>. 12/20/2021, Vol. 2021, p1-6. 6p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Accelerator-driven+systems%22">Accelerator-driven systems</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactors%22">Nuclear reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Neutrons%22">Neutrons</searchLink><br /><searchLink fieldCode="DE" term="%22Proton+beams%22">Proton beams</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+flux%22">Neutron flux</searchLink><br /><searchLink fieldCode="DE" term="%22Research+reactors%22">Research reactors</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: In this paper, the accelerator-driven subcritical reactor (ADSR) is simulated based on structure of the TRIGA-Mark II reactor. A proton beam is accelerated and interacts on the lead target. Two cases of using lead are considered here: firstly, solid lead is referred to as spallation neutron target and water as the coolant; secondly, molten lead is considered both as a target and as a coolant. The proton beam in the energy range from 115 MeV to 2000 MeV interacts with the lead to create neutrons. The neutron parameters as neutron yield Yn/p, neutron multiplication factor k, the radial and axial distributions of the neutron flux in the core have been calculated by using MCNPX program. The results show that the neutron yield increases as the energies of the proton beam increases. When using the lead target, the differences between the neutron yield are from 4.2% to 14.2% depending on the energies of the proton beam. The proportion of uranium in the mixtures should be around 24% to produce an effective neutron multiplier factor greater than 0.9. The neutron fluxes are much higher than the same calculations for the TRIGA-Mark II reactor model using tungsten target and light water coolant. [ABSTRACT FROM AUTHOR] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Science & Technology of Nuclear Installations is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.) |
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| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1155/2021/5284580 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 6 StartPage: 1 Subjects: – SubjectFull: Accelerator-driven systems Type: general – SubjectFull: Nuclear reactors Type: general – SubjectFull: Neutrons Type: general – SubjectFull: Proton beams Type: general – SubjectFull: Neutron flux Type: general – SubjectFull: Research reactors Type: general Titles: – TitleFull: Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Tran Minh, Tien – PersonEntity: Name: NameFull: Tran Quoc, Dung IsPartOfRelationships: – BibEntity: Dates: – D: 20 M: 12 Text: 12/20/2021 Type: published Y: 2021 Identifiers: – Type: issn-print Value: 16876075 Numbering: – Type: volume Value: 2021 Titles: – TitleFull: Science & Technology of Nuclear Installations Type: main |
| ResultId | 1 |
