DocumentCode :
2724909
Title :
Activation and waste disposal of the ARIES-II tokamak fusion power reactor
Author :
Khater, Hesham Y.
Author_Institution :
Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
Volume :
2
fYear :
1993
fDate :
11-15 Oct 1993
Firstpage :
930
Abstract :
A detailed activation analysis has been performed for the tokamak fusion power reactor ARIES-II. The reactor uses vanadium alloy as a structural material and liquid lithium as a coolant and tritium breeder. The total activity produced in the reactor at shutdown is 3848 MCi and drops to only 59 MCi during the first year following shutdown. Calculations of the decay heat showed that it is 53 MW at shutdown and it takes a relatively short time (<1 day) to decay by about a factor of 10. One week after shutdown, the values of the integrated decay heat generated in the structure are 548 and 1298 GJ for the reactor inboard and outboard regions, respectively. This heat represents less than 2% of the reactor thermal power and hence does not present a safety hazard. The biological hazard potential was calculated according to the NRC regulations specified in 10CFR20. The total BHP at shutdown is 388 x 10 6m3 air. The radwaste classification of the ARIES-II structure has been evaluated according to both the NRC 10CFR61 and Fetter waste disposal concentration limits. Except for the reactor outboard blanket which would qualify as Class A low level waste, the rest of the reactor structure would only qualify for Class C rating. The outboard blanket has a Class A rating value of 0.95 which is based on allowing it to cool down for about 10 years following the end of the reactor lifetime
Keywords :
Tokamak devices; fusion reactor safety; radioactive waste disposal; 3848E6 Ci; 59E6 Ci; ARIES-II; Class A waste; Class C waste; Fetter waste disposal; Li; activation; biological hazard potential; decay heat; inboard region; integrated decay heat; liquid Li; outboard blanket; outboard region; radwaste classification; shutdown; tokamak; waste disposal; Activation analysis; Biohazards; Coolants; Hazards; Inductors; Lithium; Radioactive waste disposal; Safety; Tokamaks; Waste disposal;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
Conference_Location :
Hyannis, MA
Print_ISBN :
0-7803-1412-3
Type :
conf
DOI :
10.1109/FUSION.1993.518477
Filename :
518477
Link To Document :
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