Thermal durability of modified synroc material as reactor fuel matrix.
Material type:
TextLanguage: en Publication details: Ibaraki-ken : Japan Atomic Energy Research Institute, 1994.Description: 20 p
| Item type | Home library | Call number | Status | Barcode | |
|---|---|---|---|---|---|
Books
|
Centro de Información Eduardo Savino | JAERI-Research 94-008 (Browse shelf(Opens below)) | Available | 45059 |
Total holds: 0
Browsing Centro de Información Eduardo Savino shelves Close shelf browser (Hides shelf browser)
| No cover image available | No cover image available | No cover image available | No cover image available | No cover image available | No cover image available | No cover image available | ||
| JAERI-Research 94-001 Transport studies of tokamak plasmas in JT-60 device. | JAERI-Research 94-006 Behavior of pre-irradiated fuel under a simulated ria condition [results of NSRR test JM-3]. | JAERI-Research 94-007 3-D thermal stress analysis of hot spots in reactor piping using bem. | JAERI-Research 94-008 Thermal durability of modified synroc material as reactor fuel matrix. | JAERI-Research 94-011 Onset of elms in JT-60U. | JAERI-Research 94-013 Stability analysis of external kink mode for iter l-mode profile plasmas. | JAERI-Research 94-015 Irradiation experiments of low copper A533B steels for reactor pressure vessel tested in JMTR. |
There are no comments on this title.
Log in to your account to post a comment.
