View in EDS

Design of a novel nondestructive portable mobile neutron activation system.

Saved in:
Bibliographic Details
Title: Design of a novel nondestructive portable mobile neutron activation system.
Authors: Abdelati, M.1, El Mongy, Sayed A.1, Abdelsalam, A.2
Source: Measurement (02632241). Jan2018, Vol. 114, p60-68. 9p.
Subjects: Mobile computing equipment, Nuclear activation analysis, Neutron flux, Monte Carlo method, Irradiation, Polyethylene, Paraffin wax
Abstract: A new non-destructive portable mobile system was designed to be used for neutron activation assay according to the Safeguards purposes. The sample is irradiated in a neutron field and its composition is determined by identifying the characteristic induced gamma radiation emitted by the fission and activation products. For the design of a neutron activation system, many aspects must be considered such as choosing the best materials to assure the protection against radiation and estimating the thickness required to shield the neutron source based on its flux or strength. The polyethylene and paraffin wax were selected as neutron shielding material, lead being chosen as gamma shielding material. Several calculations were performed using the Monte Carlo code MCNP5 to estimate the required shield thickness and distribution of thermal neutron flux at different irradiation position inside the shield. The available 252 Cf neutron source with 12 µCi of activity was used. The novel neutron activation analysis system was proposed, designed and fabricated to meet the maximum flexibility for neutron activation analysis, at minimum cost and with adequate optimized shielding and portability. [ABSTRACT FROM AUTHOR]
Copyright of Measurement (02632241) is the property of Elsevier B.V. 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 Text:
  Availability: 0
Header DbId: egs
DbLabel: Engineering Source
An: 126210174
AccessLevel: 6
PubType: Academic Journal
PubTypeId: academicJournal
PreciseRelevancyScore: 0
IllustrationInfo
Items – Name: Title
  Label: Title
  Group: Ti
  Data: Design of a novel nondestructive portable mobile neutron activation system.
– Name: Author
  Label: Authors
  Group: Au
  Data: <searchLink fieldCode="AR" term="%22Abdelati%2C+M%2E%22">Abdelati, M.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22El+Mongy%2C+Sayed+A%2E%22">El Mongy, Sayed A.</searchLink><relatesTo>1</relatesTo><br /><searchLink fieldCode="AR" term="%22Abdelsalam%2C+A%2E%22">Abdelsalam, A.</searchLink><relatesTo>2</relatesTo>
– Name: TitleSource
  Label: Source
  Group: Src
  Data: <searchLink fieldCode="JN" term="%22Measurement+%2802632241%29%22">Measurement (02632241)</searchLink>. Jan2018, Vol. 114, p60-68. 9p.
– Name: Subject
  Label: Subjects
  Group: Su
  Data: <searchLink fieldCode="DE" term="%22Mobile+computing+equipment%22">Mobile computing equipment</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+activation+analysis%22">Nuclear activation analysis</searchLink><br /><searchLink fieldCode="DE" term="%22Neutron+flux%22">Neutron flux</searchLink><br /><searchLink fieldCode="DE" term="%22Monte+Carlo+method%22">Monte Carlo method</searchLink><br /><searchLink fieldCode="DE" term="%22Irradiation%22">Irradiation</searchLink><br /><searchLink fieldCode="DE" term="%22Polyethylene%22">Polyethylene</searchLink><br /><searchLink fieldCode="DE" term="%22Paraffin+wax%22">Paraffin wax</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: A new non-destructive portable mobile system was designed to be used for neutron activation assay according to the Safeguards purposes. The sample is irradiated in a neutron field and its composition is determined by identifying the characteristic induced gamma radiation emitted by the fission and activation products. For the design of a neutron activation system, many aspects must be considered such as choosing the best materials to assure the protection against radiation and estimating the thickness required to shield the neutron source based on its flux or strength. The polyethylene and paraffin wax were selected as neutron shielding material, lead being chosen as gamma shielding material. Several calculations were performed using the Monte Carlo code MCNP5 to estimate the required shield thickness and distribution of thermal neutron flux at different irradiation position inside the shield. The available 252 Cf neutron source with 12 µCi of activity was used. The novel neutron activation analysis system was proposed, designed and fabricated to meet the maximum flexibility for neutron activation analysis, at minimum cost and with adequate optimized shielding and portability. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Measurement (02632241) is the property of Elsevier B.V. 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.)
PLink https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&db=egs&AN=126210174
RecordInfo BibRecord:
  BibEntity:
    Identifiers:
      – Type: doi
        Value: 10.1016/j.measurement.2017.09.005
    Languages:
      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 9
        StartPage: 60
    Subjects:
      – SubjectFull: Mobile computing equipment
        Type: general
      – SubjectFull: Nuclear activation analysis
        Type: general
      – SubjectFull: Neutron flux
        Type: general
      – SubjectFull: Monte Carlo method
        Type: general
      – SubjectFull: Irradiation
        Type: general
      – SubjectFull: Polyethylene
        Type: general
      – SubjectFull: Paraffin wax
        Type: general
    Titles:
      – TitleFull: Design of a novel nondestructive portable mobile neutron activation system.
        Type: main
  BibRelationships:
    HasContributorRelationships:
      – PersonEntity:
          Name:
            NameFull: Abdelati, M.
      – PersonEntity:
          Name:
            NameFull: El Mongy, Sayed A.
      – PersonEntity:
          Name:
            NameFull: Abdelsalam, A.
    IsPartOfRelationships:
      – BibEntity:
          Dates:
            – D: 15
              M: 01
              Text: Jan2018
              Type: published
              Y: 2018
          Identifiers:
            – Type: issn-print
              Value: 02632241
          Numbering:
            – Type: volume
              Value: 114
          Titles:
            – TitleFull: Measurement (02632241)
              Type: main
ResultId 1