Simulation of large-scale air detritiation operations by computer modeling and bench-scale experimentation
A time-dependent computer model was developed to study the effects of various reaction and soaking mechanisms that could occur in a typically-sized reactor building (approximately 10/sup 5/ m/sup 3/) following a range of tritium releases (2 to 200 grams). In parallel with the computer study a small (approximately 50 l) test chamber was set up to investigate cleanup characteristics under conditions which could also be simulated with the computer code. Whereas results of computer analyses indicated that only approximately 10/sup -3/ percent of the tritium released to an ambient enclosure should be converted to tritiated water, the bench scale experiments gave evidence of conversions to water greater than 1 percent. Furthermore, although the amounts of soaked tritium (both calculated and observed) are usually only a very small fraction of the total tritium release, the soaked tritium is significant, in that its continuous return to the enclosure extends the cleanup time beyond the predicted value in the absence of soaking mechanisms. Where rapid detritiation of an enclosure to the recommended radiation control guideline level (5 ..mu..Ci/m/sup 3/ for HTO) is required, there may be some incentive for venting and flushing of the enclosure toward the end of the cleanup operation.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 6891120
- Report Number(s):
- ANL/FPP-77-3
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BUILDINGS
TRITIUM RECOVERY
THERMONUCLEAR REACTORS
TRITIUM
REMOVAL
CLEANING
COMPUTER CALCULATIONS
COMPUTER CODES
CONTAINMENT
SIMULATION
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
RECOVERY
YEARS LIVING RADIOISOTOPES
700206* - Fusion Power Plant Technology- Environmental Aspects