Materials for Nuclear Waste Immobilization
The book outlines recent advances in nuclear wasteform materials including glasses, ceramics and cements and spent nuclear fuel. It focuses on durability aspects and contains data on performance of nuclear wasteforms as well as expected behavior in a disposal environment.
محفوظ في:
| المؤلفون الرئيسيون: | , |
|---|---|
| التنسيق: | Online |
| اللغة: | الإنجليزية |
| منشور في: |
MDPI - Multidisciplinary Digital Publishing Institute
2021
|
| الموضوعات: | |
| الوصول للمادة أونلاين: | 43624 |
| الوسوم: |
لا توجد وسوم, كن أول من يضع وسما على هذه التسجيلة!
|
| _version_ | 1869530273072283648 |
|---|---|
| author | Ojovan, Michael I Hyatt, Neil C. |
| author_browse | Hyatt, Neil C. Ojovan, Michael I |
| author_facet | Ojovan, Michael I Hyatt, Neil C. |
| author_sort | Ojovan, Michael I |
| collection | Directory of Open Access Books |
| description | The book outlines recent advances in nuclear wasteform materials including glasses, ceramics and cements and spent nuclear fuel. It focuses on durability aspects and contains data on performance of nuclear wasteforms as well as expected behavior in a disposal environment. |
| format | Online |
| id | doab-20.500.12854ir-52862 |
| institution | Directory of Open Access Books |
| language | eng |
| publishDate | 2021 |
| publishDateRange | 2021 |
| publishDateSort | 2021 |
| publisher | MDPI - Multidisciplinary Digital Publishing Institute |
| publisherStr | MDPI - Multidisciplinary Digital Publishing Institute |
| record_format | ojs |
| spelling | doab-20.500.12854ir-528622024-04-11T15:10:36Z Materials for Nuclear Waste Immobilization Ojovan, Michael I Hyatt, Neil C. TA1-2040 T1-995 actinides corrosion modeling paper sludge ash americium geological repository seawater burnup credit spark plasma sintering glass composite materials spent nuclear fuel leaching processes zeolite polymer composite fiber crystalline ceramics glass lanthanum inorganic synthesis durability leaching layered double hydroxides LDH plutonium sedimentation conditioning criticality safety uranium radionuclide sintering vitrification rare earth elements loading curves silver iodide forward dissolution rate caesium phosphomolybdate waste form fractional release alkali borosilicate glass immobilisation iodine lesukite geopolymer radioactive cesium ceramics cesium adsorbed immobilization wasteforms secondary phases cesium safe storage borosilicate glass corrosion research reactor fuel element U3Si2-Al strontium in situ fluid-cell Raman spectroscopy magnesium potassium phosphate compound chlorine neodymium zirconium molybdate heavy ion irradiation nuclear waste microscopy hazardous water thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues::TBX History of engineering and technology The book outlines recent advances in nuclear wasteform materials including glasses, ceramics and cements and spent nuclear fuel. It focuses on durability aspects and contains data on performance of nuclear wasteforms as well as expected behavior in a disposal environment. 2021-02-11T18:54:39Z 2021-02-11T18:54:39Z 2020-01-30 16:39:46 2020 book 43624 9783039218462 9783039218479 https://directory.doabooks.org/handle/20.500.12854/52862 eng application/octet-stream Attribution-NonCommercial-NoDerivatives 4.0 International https://www.mdpi.com/books/pdfview/book/1934 https://www.mdpi.com/books/pdfview/book/1934 MDPI - Multidisciplinary Digital Publishing Institute 10.3390/books978-3-03921-847-9 10.3390/books978-3-03921-847-9 46cabcaa-dd94-4bfe-87b4-55023c1b36d0 9783039218462 9783039218479 220 open access |
| spellingShingle | TA1-2040 T1-995 actinides corrosion modeling paper sludge ash americium geological repository seawater burnup credit spark plasma sintering glass composite materials spent nuclear fuel leaching processes zeolite polymer composite fiber crystalline ceramics glass lanthanum inorganic synthesis durability leaching layered double hydroxides LDH plutonium sedimentation conditioning criticality safety uranium radionuclide sintering vitrification rare earth elements loading curves silver iodide forward dissolution rate caesium phosphomolybdate waste form fractional release alkali borosilicate glass immobilisation iodine lesukite geopolymer radioactive cesium ceramics cesium adsorbed immobilization wasteforms secondary phases cesium safe storage borosilicate glass corrosion research reactor fuel element U3Si2-Al strontium in situ fluid-cell Raman spectroscopy magnesium potassium phosphate compound chlorine neodymium zirconium molybdate heavy ion irradiation nuclear waste microscopy hazardous water thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues::TBX History of engineering and technology Ojovan, Michael I Hyatt, Neil C. Materials for Nuclear Waste Immobilization |
| title | Materials for Nuclear Waste Immobilization |
| title_full | Materials for Nuclear Waste Immobilization |
| title_fullStr | Materials for Nuclear Waste Immobilization |
| title_full_unstemmed | Materials for Nuclear Waste Immobilization |
| title_short | Materials for Nuclear Waste Immobilization |
| title_sort | materials for nuclear waste immobilization |
| topic | TA1-2040 T1-995 actinides corrosion modeling paper sludge ash americium geological repository seawater burnup credit spark plasma sintering glass composite materials spent nuclear fuel leaching processes zeolite polymer composite fiber crystalline ceramics glass lanthanum inorganic synthesis durability leaching layered double hydroxides LDH plutonium sedimentation conditioning criticality safety uranium radionuclide sintering vitrification rare earth elements loading curves silver iodide forward dissolution rate caesium phosphomolybdate waste form fractional release alkali borosilicate glass immobilisation iodine lesukite geopolymer radioactive cesium ceramics cesium adsorbed immobilization wasteforms secondary phases cesium safe storage borosilicate glass corrosion research reactor fuel element U3Si2-Al strontium in situ fluid-cell Raman spectroscopy magnesium potassium phosphate compound chlorine neodymium zirconium molybdate heavy ion irradiation nuclear waste microscopy hazardous water thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues::TBX History of engineering and technology |
| topic_facet | TA1-2040 T1-995 actinides corrosion modeling paper sludge ash americium geological repository seawater burnup credit spark plasma sintering glass composite materials spent nuclear fuel leaching processes zeolite polymer composite fiber crystalline ceramics glass lanthanum inorganic synthesis durability leaching layered double hydroxides LDH plutonium sedimentation conditioning criticality safety uranium radionuclide sintering vitrification rare earth elements loading curves silver iodide forward dissolution rate caesium phosphomolybdate waste form fractional release alkali borosilicate glass immobilisation iodine lesukite geopolymer radioactive cesium ceramics cesium adsorbed immobilization wasteforms secondary phases cesium safe storage borosilicate glass corrosion research reactor fuel element U3Si2-Al strontium in situ fluid-cell Raman spectroscopy magnesium potassium phosphate compound chlorine neodymium zirconium molybdate heavy ion irradiation nuclear waste microscopy hazardous water thema EDItEUR::T Technology, Engineering, Agriculture, Industrial processes::TB Technology: general issues::TBX History of engineering and technology |
| url | 43624 |
| work_keys_str_mv | AT ojovanmichaeli materialsfornuclearwasteimmobilization AT hyattneilc materialsfornuclearwasteimmobilization |