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FLUORIDE-SALT-COOLED HIGH-TEMPERATURE REACTOR (FHR) WITH SILICON-CARBIDE-MATRIX COATED-PARTICLE FUEL. (S&T Issue 2013-04)(CD-ROM) (DE20121047644 ; DE20121047644)

FLUORIDE-SALT-COOLED HIGH-TEMPERATURE REACTOR (FHR) WITH SILICON-CARBIDE-MATRIX COATED-PARTICLE FUEL. (S&T Issue 2013-04)(CD-ROM) (DE20121047644 ; DE20121047644)
Paper図書
FORSBERG, C.W.(et al.)2012.
Other Libraries in Japan
  • Author HeadingFORSBERG, C.W.

Alternative repository criticality-control strategies for fissile uranium wastes ORNLCP97687 DE98 003504

Alternative repository criticality-control strategies for fissile uranium wastes ORNLCP97687 DE98 003504
Microform規格・テクニカルリポート類
Forsberg, C. W1998<LS-DE98/003504>
National Diet Library

Recovery of fissile materials from plutonium residues, miscellaneous spent nuclear fuel, and uranium fissile wastes CONF-970321-3 DE97 003499

Recovery of fissile materials from plutonium residues, miscellaneous spent nuclear fuel, and uranium fissile wastes CONF-970321-3 DE97 003499
Microform規格・テクニカルリポート類
Forsberg, C. W1997<LS-DE97/003499>
National Diet Library

Disposition options for U-233 ORNLCP97933 DE98 003515 CONF980906

Disposition options for U-233 ORNLCP97933 DE98 003515 CONF980906
Microform規格・テクニカルリポート類
Forsberg, C. W, Icenhour, A. S, Krichinsky, A. M1998<LS-DE98/003515>
National Diet Library

Depleted uranium oxides as spent-nuclear-fuel waste-package fill materials CONF-970793-1 DE97 008242

Depleted uranium oxides as spent-nuclear-fuel waste-package fill materials CONF-970793-1 DE97 008242
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W1997<LS-DE97/008242>
National Diet LibraryOther Libraries in Japan

Underground reactor containments: An option for the future CONF-970649-3 DE97 004286

Underground reactor containments: An option for the future CONF-970649-3 DE97 004286
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W, Kress, T1997<LS-DE97/004286>
National Diet LibraryOther Libraries in Japan

Long-term criticality control in radioactive waste disposal facilities using depleted uranium CONF-970926-3 DE97 003492

Long-term criticality control in radioactive waste disposal facilities using depleted uranium CONF-970926-3 DE97 003492
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W1997<LS-DE97/003492>
National Diet LibraryOther Libraries in Japan

Depleted uranium oxides as spent-nuclear-fuel waste-package invert and backfill materials CONF-970793-2 DE97 008241

Depleted uranium oxides as spent-nuclear-fuel waste-package invert and backfill materials CONF-970793-2 DE97 008241
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W, Haire, M. J1997<LS-DE97/008241>
National Diet LibraryOther Libraries in Japan

Strategy for the future use and disposition of Uranium-233: History, inventories, storage facilities, and potential future uses ORNLTM13551 DE99 000345

Strategy for the future use and disposition of Uranium-233: History, inventories, storage facilities, and potential future uses ORNLTM13551 DE99 000345
Microform規格・テクニカルリポート類
Bereolos, P. J, Lewis, L. C, Forsberg, C. W, Storch, S. N, Krichinsky, A. M1998<LS-DE99/000345>
National Diet Library

Glass material oxidation and dissolution system: Converting miscellaneous fissile materials to glass CONF-9606116-8 DE96 008654

Glass material oxidation and dissolution system: Converting miscellaneous fissile materials to glass CONF-9606116-8 DE96 008654
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W, Ferrada, J. J1996<LS-DE96/008654>
National Diet LibraryOther Libraries in Japan

Use of depleted uranium silicate glass to minimize release of radionuclides from spent nuclear fuel waste packages CONF-960271-3 DE96 006707

Use of depleted uranium silicate glass to minimize release of radionuclides from spent nuclear fuel waste packages CONF-960271-3 DE96 006707
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W1996<LS-DE96/006707>
National Diet LibraryOther Libraries in Japan

US Light-Water Reactor spent fuel inventory-fissile distribution CONF-960421-4 DE96 004934

US Light-Water Reactor spent fuel inventory-fissile distribution CONF-960421-4 DE96 004934
PaperMicroform規格・テクニカルリポート類
Ashline, R. C, Forsberg, C. W1995<LS-DE96/004934>
National Diet LibraryOther Libraries in Japan

Isotopic dilution of (sup 233)U with depleted uranium for criticality safety in processing and disposal CONF-970926-9 DE97 006434

Isotopic dilution of (sup 233)U with depleted uranium for criticality safety in processing and disposal CONF-970926-9 DE97 006434
PaperMicroform規格・テクニカルリポート類
Hopper, C. M, Wright, R. Q, Elam, K. R, Forsberg, C. W1997<LS-DE97/006434>
National Diet LibraryOther Libraries in Japan

What is plutonium stabilization, and what is safe storage of plutonium ORNL/M-4322 DE96 000835

What is plutonium stabilization, and what is safe storage of plutonium ORNL/M-4322 DE96 000835
Microform規格・テクニカルリポート類
Forsberg, C. W1995<LS-DE96/000835>
National Diet Library

Conversion of ion-exchange resins, catalysts and sludges to glass with optional noble metal recovery using the GMODS process CONF-961108-1 DE97 000621

Conversion of ion-exchange resins, catalysts and sludges to glass with optional noble metal recovery using the GMODS process CONF-961108-1 DE97 000621
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W, Beahm, E. C1996<LS-DE97/000621>
National Diet LibraryOther Libraries in Japan

New glass material oxidation and dissolution system facility: Direct conversion of surplus fissile materials, spent nuclear fuel, and other material to high-level-waste glass. Storage and disposition of weapons-usable fissile materials programmatic... ORNL/MD/LTR-13 DE95 011767

New glass material oxidation and dissolution system facility: Direct conversion of surplus fissile materials, spent nuclear fuel, and other material to high-level-waste glass. Storage and disposition of weapons-usable fissile materials programmatic... ORNL/MD/LTR-13 DE95 011767
Microform規格・テクニカルリポート類
Forsberg, C. W, Elam, K. R, Reich, W. J1995<LS-DE95/011767>
National Diet Library

Preliminary process simulation and analysis of GMODS: Processing of plutonium surplus materials ORNL/TM-13109 DE96 006579

Preliminary process simulation and analysis of GMODS: Processing of plutonium surplus materials ORNL/TM-13109 DE96 006579
Microform規格・テクニカルリポート類
Ferrada, J. J, Nehls, J. W, Welch, T. D, Giardina, J. L, Forsberg, C. W1996<LS-DE96/006579>
National Diet Library

Direct conversion of halogen-containing wastes to borosilicate glass CONF-961202-15 DE97 001733

Direct conversion of halogen-containing wastes to borosilicate glass CONF-961202-15 DE97 001733
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W, Beahm, E. C, Rudolph, J. C1996<LS-DE97/001733>
National Diet LibraryOther Libraries in Japan

Shielding analysis of depleted uranium silicate filler concept for spent fuel canister designs CONF-960415-33 DE96 008090

Shielding analysis of depleted uranium silicate filler concept for spent fuel canister designs CONF-960415-33 DE96 008090
PaperMicroform規格・テクニカルリポート類
DeHart, M. D, Tang, J. S, Forsberg, C. W1996<LS-DE96/008090>
National Diet LibraryOther Libraries in Japan

Conversion of plutonium-containing materials into borosilicate glass using the glass material oxidation and dissolution system CONF-960271-4 DE96 006706

Conversion of plutonium-containing materials into borosilicate glass using the glass material oxidation and dissolution system CONF-960271-4 DE96 006706
PaperMicroform規格・テクニカルリポート類
Forsberg, C. W, Beahm, E. C, Parker, G. W1996<LS-DE96/006706>
National Diet LibraryOther Libraries in Japan
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