PT-IP-759, channel caulking tests: C Reactor
The graphite movement which has occurred at the various reactors has been characterized by two problems: (1) Crooked channels and (2) cracks and miscellaneous voids where pieces of blocks are missing. Of these problems, the cracks and voids have been the most serious in the case of ball drops. Alleviation of the crooked channels can sometimes be accomplished by graphite removal methods such as broaching, but unless some method is found to prevent the balls from entering cracks, the total effect of a ball drop would still be intolerable. Of the two methods of closing the cracks, a paste caulking procedure is anticipated to be less expensive than sleeving, both in terms of cost of the operation and the number of process tube channels which might be lost. If the VSR channel does not require drastic straightening or entry of large tooling, satisfactory caulking can be done without removal of the step plug. ``Poison`` chain may be considered as an alternative to caulking or sleeving for those outer VSR channels where the sole use of balls is for ``total control`` rather than ``speed of control.`` The objectives of this test are (1) to authorize the experimental crack filling of one or two of the VSR channels at C Reactor with a wet mixture of graphite and sugar, (2) to demonstrate the durability of this mixture in subsequent normal reactor operation, and (3) to demonstrate by testing (actual or simulated ball drops) and borescoping, that the channels are or are not again acceptable for use with the normal charge of balls.
- Research Organization:
- General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10169121
- Report Number(s):
- RL-REA-697; ON: DE94015577
- Resource Relation:
- Other Information: DN: Declassified; PBD: 19 Mar 1965
- Country of Publication:
- United States
- Language:
- English
Similar Records
DR Reactor VSR channel damage
Design test request No. 1263 K Reactor graphite key and VSR channel sleeve test