Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor

التفاصيل البيبلوغرافية
العنوان: Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor
المؤلفون: Gholamzadeh, Z., Mirvakili, S. M., Davari, A., Alizadeh, M., Joz-Vaziri, A.
المصدر: Nukleonika.
مصطلحات موضوعية: research reactor, 99Mo production, uranyl sulphate, liquid target, MCNPX code
الوصف: The activation method for 99Mo production in comparison to fi ssionable target irradiation in research reactors is less preferable. Therefore, 99Mo yield using UO2SO4 samples was theoretically investigated. Computational results revealed admirable potential of the liquid samples for 99Mo production. Low-concentrated uranyl sulphate samples could easily be handled by the irradiation box. The sample geometry optimization improves thermal hydraulic conditions and production yield. The optimized geometry including only 0.12 g 235U produced 57Ci99Mo at end-of-irradiation (EOI) with a temperature peak of 72°C during the irradiation.
نوع الوثيقة: Article
اللغة: English
URL الوصول: http://yadda.icm.edu.pl/baztech/element/bwmeta1.element.baztech-3ea99b76-8ceb-4e43-9ab6-a21e2c13e130
رقم الانضمام: edsbzt.bwmeta1.element.baztech.3ea99b76.8ceb.4e43.9ab6.a21e2c13e130
قاعدة البيانات: BazTech
ResultId 1
Header edsbzt
BazTech
edsbzt.bwmeta1.element.baztech.3ea99b76.8ceb.4e43.9ab6.a21e2c13e130
740
3
Periodical
serialPeriodical
740
PLink https://search.ebscohost.com/login.aspx?direct=true&site=eds-live&scope=site&db=edsbzt&AN=edsbzt.bwmeta1.element.baztech.3ea99b76.8ceb.4e43.9ab6.a21e2c13e130&custid=s6537998&authtype=sso
FullText Array ( [Availability] => 0 )
Array ( [0] => Array ( [Url] => http://yadda.icm.edu.pl/baztech/element/bwmeta1.element.baztech-3ea99b76-8ceb-4e43-9ab6-a21e2c13e130 [Name] => EDS - BazTech [Category] => fullText [Text] => View record in BazTech [MouseOverText] => View record in BazTech ) )
Items Array ( [Name] => Title [Label] => Title [Group] => Ti [Data] => Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor )
Array ( [Name] => Author [Label] => Authors [Group] => Au [Data] => <searchLink fieldCode="AR" term="%22Gholamzadeh%2C+Z%2E%22">Gholamzadeh, Z.</searchLink><br /><searchLink fieldCode="AR" term="%22Mirvakili%2C+S%2E+M%2E%22">Mirvakili, S. M.</searchLink><br /><searchLink fieldCode="AR" term="%22Davari%2C+A%2E%22">Davari, A.</searchLink><br /><searchLink fieldCode="AR" term="%22Alizadeh%2C+M%2E%22">Alizadeh, M.</searchLink><br /><searchLink fieldCode="AR" term="%22Joz-Vaziri%2C+A%2E%22">Joz-Vaziri, A.</searchLink> )
Array ( [Name] => TitleSource [Label] => Source [Group] => Src [Data] => <i>Nukleonika</i>. )
Array ( [Name] => Subject [Label] => Subject Terms [Group] => Su [Data] => <searchLink fieldCode="DE" term="%22research+reactor%22">research reactor</searchLink><br /><searchLink fieldCode="DE" term="%2299Mo+production%22">99Mo production</searchLink><br /><searchLink fieldCode="DE" term="%22uranyl+sulphate%22">uranyl sulphate</searchLink><br /><searchLink fieldCode="DE" term="%22liquid+target%22">liquid target</searchLink><br /><searchLink fieldCode="DE" term="%22MCNPX+code%22">MCNPX code</searchLink> )
Array ( [Name] => Abstract [Label] => Description [Group] => Ab [Data] => The activation method for 99Mo production in comparison to fi ssionable target irradiation in research reactors is less preferable. Therefore, 99Mo yield using UO2SO4 samples was theoretically investigated. Computational results revealed admirable potential of the liquid samples for 99Mo production. Low-concentrated uranyl sulphate samples could easily be handled by the irradiation box. The sample geometry optimization improves thermal hydraulic conditions and production yield. The optimized geometry including only 0.12 g 235U produced 57Ci99Mo at end-of-irradiation (EOI) with a temperature peak of 72°C during the irradiation. )
Array ( [Name] => TypeDocument [Label] => Document Type [Group] => TypDoc [Data] => Article )
Array ( [Name] => Language [Label] => Language [Group] => Lang [Data] => English )
Array ( [Name] => URL [Label] => Access URL [Group] => URL [Data] => <link linkTarget="URL" linkTerm="http://yadda.icm.edu.pl/baztech/element/bwmeta1.element.baztech-3ea99b76-8ceb-4e43-9ab6-a21e2c13e130" linkWindow="_blank">http://yadda.icm.edu.pl/baztech/element/bwmeta1.element.baztech-3ea99b76-8ceb-4e43-9ab6-a21e2c13e130</link> )
Array ( [Name] => AN [Label] => Accession Number [Group] => ID [Data] => edsbzt.bwmeta1.element.baztech.3ea99b76.8ceb.4e43.9ab6.a21e2c13e130 )
RecordInfo Array ( [BibEntity] => Array ( [Languages] => Array ( [0] => Array ( [Text] => English ) ) [Subjects] => Array ( [0] => Array ( [SubjectFull] => research reactor [Type] => general ) [1] => Array ( [SubjectFull] => 99Mo production [Type] => general ) [2] => Array ( [SubjectFull] => uranyl sulphate [Type] => general ) [3] => Array ( [SubjectFull] => liquid target [Type] => general ) [4] => Array ( [SubjectFull] => MCNPX code [Type] => general ) ) [Titles] => Array ( [0] => Array ( [TitleFull] => Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor [Type] => main ) ) ) [BibRelationships] => Array ( [HasContributorRelationships] => Array ( [0] => Array ( [PersonEntity] => Array ( [Name] => Array ( [NameFull] => Gholamzadeh, Z. ) ) ) [1] => Array ( [PersonEntity] => Array ( [Name] => Array ( [NameFull] => Mirvakili, S. M. ) ) ) [2] => Array ( [PersonEntity] => Array ( [Name] => Array ( [NameFull] => Davari, A. ) ) ) [3] => Array ( [PersonEntity] => Array ( [Name] => Array ( [NameFull] => Alizadeh, M. ) ) ) [4] => Array ( [PersonEntity] => Array ( [Name] => Array ( [NameFull] => Joz-Vaziri, A. ) ) ) ) [IsPartOfRelationships] => Array ( [0] => Array ( [BibEntity] => Array ( [Titles] => Array ( [0] => Array ( [TitleFull] => Nukleonika [Type] => main ) ) ) ) ) ) )
IllustrationInfo