المؤلفون: YUMAK, Tuğrul

المصدر: Volume: 8, Issue: 2 169-177 ; 2536-4383 ; 2564-7873 ; Sinop University Journal of Natural Sciences ; Sinop Üniversitesi Fen Bilimleri Dergisi

مصطلحات موضوعية: Graphite, expansion of graphite, g-C3N4, thermal treatment, Grafit, grafitin genişlemesi, ısıl işlemler, Material Production Technologies, Malzeme Üretim Teknolojileri

وصف الملف: application/pdf

Relation: https://dergipark.org.tr/tr/download/article-file/3434969; https://dergipark.org.tr/tr/pub/sinopfbd/issue/81939/1366684

الاتاحة: https://dergipark.org.tr/tr/pub/sinopfbd/issue/81939/1366684
https://doi.org/10.33484/sinopfbd.1366684

المساهمون: Helm, J

المصدر: Other Information: UNCL. Orig. Receipt Date: 31-DEC-69

وصف الملف: Medium: ED; Size: Pages: 98

URL الوصول: http://www.osti.gov/scitech/servlets/purl/4778830

المصدر: Other Information: Contains reports BNL-275(Del.) and BNL-255. Orig. Receipt Date: 31-DEC-59

وصف الملف: Medium: ED; Size: Pages: 225

URL الوصول: http://www.osti.gov/scitech/servlets/purl/4277594

المساهمون: Price, R

المصدر: Other Information: UNCL. Orig. Receipt Date: 31-DEC-72

وصف الملف: Medium: ED; Size: Pages: 20

URL الوصول: http://www.osti.gov/scitech/servlets/purl/4702969

المساهمون: Faris, F.E.

المصدر: Other Information: Decl. Feb. 7, 1957. Orig. Receipt Date: 31-DEC-57

وصف الملف: Medium: X; Size: Pages: 63

URL الوصول: http://www.osti.gov/scitech/biblio/4352062

المصدر: Other Information: UNCL. Orig. Receipt Date: 31-DEC-67

وصف الملف: Medium: X; Size: Pages: 84

URL الوصول: http://www.osti.gov/scitech/biblio/4341574

المصدر: Other Information: Decl. Feb. 26, 1957. Orig. Receipt Date: 31-DEC-57

وصف الملف: Medium: X; Size: Pages: 98

URL الوصول: http://www.osti.gov/scitech/biblio/4319841

المؤلفون: None

مصطلحات موضوعية: REACTORS, ABSORPTION-- BGRR-- FILTERS-- FISSION PRODUCTS-- REACTOR SAFETY-- REACTORS-- RESEARCH REACTORS-- VOLATILITY, ABSORPTION-- BGRR-- FISSION PRODUCTS-- FUEL ELEMENTS-- MELTING-- PLATES-- REACTOR SAFETY-- REACTORS-- RESEARCH REACTORS-- VOLATILITY, ANNEALING-- BGRR-- COMBUSTION-- CONTROL-- ENERGY-- EXPANSION-- GRAPHITE-- GRAPHITE MODERATOR-- HIGH TEMPERATURE-- PERFORMANCE-- REACTOR CORE-- REACTOR SAFETY-- REACTORS-- RESEARCH REACTORS-- STORAGE, BEPO-- BGRR-- CONTROL-- ENERGY-- GRAPHITE-- GRAPHITE MODERATOR-- LOW TEMPERATURE-- REACTOR SAFETY-- REACTORS-- RESEARCH REACTORS-- STORAGE, BGRR-- BURNOUT-- CONTAMINATION-- ENVIRONMENT-- FAILURES-- FUEL ELEM

وصف الملف: application/pdf

Relation: http://www.osti.gov/servlets/purl/4277594; https://www.osti.gov/biblio/4277594; https://doi.org/10.2172/4277594

الاتاحة: http://www.osti.gov/servlets/purl/4277594
https://www.osti.gov/biblio/4277594
https://doi.org/10.2172/4277594

المؤلفون: Engle, G.B., Price, R.J.

المساهمون: United States. Department of Energy.

المصدر: Other Information: UNCL. Orig. Receipt Date: 31-DEC-72

مصطلحات موضوعية: Graphite/Radiation Effects On Dimensions Of, Relations Of Crystal Structure And Density With Neutron, Coke, Expansion, Carbon, Configuration, Graphite/Radiation Effect On Thermal Expansion At 1000 To 1430$Sup 0$C, Neutron, Tensile Properties, Pyrolytic Graphite, High Temperature, Radiation Effects, Neutrons/Effects On Crystallite Size And Lattice Parameters Of Type Atj Graphite, Graphite, N30230 --Metals, Ceramics, & Other Materials--Ceramics & Cermets--Properties Evaluations, Pyrolytic Carbon, Neutrons/Effects On Density And Dimensions Of Powdered Coke, Graphite/Radiation Effects On Crystallite Size And Lattice Parameters Of Hot- Worked Type Atj, Orientation, Crystallography, Coke/ Radiation Effects On Density And Dimensions Of Powdered, Irradiation, N30250* --Metals, & Other Materials--Ceramics & Cermets--Radiation Effects, Neutrons/Effects On Dimensions Of Graphite Specimens, Relations With Crystal Structure And Density, Neutrons, Neutrons/ Effects On Thermal Expansion Of Graphite At 1000 To 1430--C

وصف الملف: 20 pages; Text

Relation: rep-no: GULF-GA-A--10863; grantno: AT(04-3)-167; osti: 4702969; https://digital.library.unt.edu/ark:/67531/metadc1030549/; ark: ark:/67531/metadc1030549

الاتاحة: https://doi.org/10.2172/4702969
https://digital.library.unt.edu/ark:/67531/metadc1030549/

المؤلفون: Helm, J.W.

المساهمون: United States. Department of Energy.

المصدر: Other Information: UNCL. Orig. Receipt Date: 31-DEC-69

مصطلحات موضوعية: Irradiation, N30250* --Metals, Ceramics, & Other Materials--Ceramics & Cermets--Radiation Effects, Temperature Graphite/Radiation Effects On Expansion Of, At 300 To 1200$Sup 0$C, Fast Neutron, High Temperature, Fast Neutrons, Expansion, Radiation Effects, Neutrons, Fast/Effects On The Expansion Of Graphite At 300 To 1200--C, Graphite, Graphite/Radiation Effects On Expansion Of

وصف الملف: Pages: 98; Text

Relation: rep-no: BNWL--1056-A; grantno: AT(45-1)-1830; osti: 4778830; https://digital.library.unt.edu/ark:/67531/metadc1059629/; ark: ark:/67531/metadc1059629

الاتاحة: https://doi.org/10.2172/4778830
https://digital.library.unt.edu/ark:/67531/metadc1059629/