| 摘要 |
FIELD: nuclear power engineering. SUBSTANCE: fuel element has retaining plate 5 with inlet 10 passing retaining rod 8a, 8b whose stop tip 11a, 11b abuts against inner surface of retaining plate 5. Locking plate 9 placed on external side of retaining plate 5 serves as a guide for safety sleeve '16a, 16b that moves in its longitudinal direction and is arranged coaxially relative to retaining rod 8a, 8b. This safety sleeve 16a, 16b is free to pierce thrust washer 15 placed above locking plate 9; compression spring 7a, 17b rests on safety sleeve 16a, 16b and thrust washer 15. It is pre-stressed by means of bracing bolt 14 which is secured on retaining plate 5, acts on thrust washer 15, and easily pierces it. Compression spring 17a, 17b presses one end of tongue to provide force closure between retaining plate 5 and retaining rod 8a, 8b in inlet 10 of retaining plate 5 between the latter and retaining rod 8a, 8b. EFFECT: facilitated handling of irradiated fuel element during its removal and recharging; more compact design of its can. 11 cl, 5 dwga |
