Published September 11, 1990 | Version v1
Patent

Pellet take-out device

Description

An annular radio frequency heater for heating a spent nuclear fuel can and an annular coolant spray pipe for cooling the spent nuclear fuel can are disposed in parallel along the axis of the pipes so as to surround the spent nuclear fuel can. This causes a great temperature slope along the axis of the pipe of the spent nuclear fuel can and causes plastic deformation expansion due to thermal ratchet strain to expand the diameter of the fuel can. In this case, since the sintered pellets of uranium dioxide are not expanded but can be taken out from the spent nuclear fuel can, use of a shearing device may be saved. Accordingly, the installation and the running costs of a reprocessing plant can be reduced and the operation efficiency and the dissolving rate can be improved. (T.M.)

Availability note (English)

Available from JAPIO. Also available from INPADOC.

Additional details

Publishing Information

Imprint Pagination
6 p.
IPC:
Int. Cl. G21C19/37.
IPC
Int. Cl. G21C19/37.
Patent number
JP patent document 2-228595/A/

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
22033582
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
CONFIGURATION; DECLADDING; DEFORMATION; EXPANSION; FUEL CANS; FUEL PELLETS; HIGH-FREQUENCY HEATING; REFRIGERANTS; REPROCESSING; SEALS; SPENT FUELS; TEMPERATURE GRADIENTS
Descriptors DEC
ENERGY SOURCES; FUELS; HEAD END PROCESSES; HEATING; MATERIALS; NUCLEAR FUELS; PLASMA HEATING; REACTOR MATERIALS; SEPARATION PROCESSES

Optional Information

Secondary number(s)
JP patent application 1-48559.