Title :
Activation analysis of the PULSAR-II fusion power reactor
Author :
Khater, Hesham Y.
Author_Institution :
Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
fDate :
30 Sep-5 Oct 1995
Abstract :
The PULSAR-II pulsed tokamak power plant design utilizes a blanket made of the vanadium alloy, V-5Cr-5Ti, and cooled with liquid lithium. The shield is made of a mixture of the low activation austenitic steel (Tenelon) and vanadium. The blanket is assumed to be replaced every 5.6 full power years (FPY) and the shield is assumed to stay in place for 30 FPY. The activity induced in the blanket at the end of its lifetime is higher than the activity induced in the shield after 30 FPY. At shutdown, the blanket and shield activities are 2678 MCi and 1747 MCi, respectively One year after shutdown the shield activity drops to 18 MCi compared to 84 MCi for the blanket. The total decay heat generated in the blanket at the end of its lifetime is 34.7 MW and drops to 17.6 MW within an hour. At shutdown, 25.3 MW of decay heat are generated in the shield, dropping to only 0.1 MW within the first year. One week after shutdown, the values of the integrated decay heat are 1770 GJ for the blanket and 469 GJ for the shield. The radwaste classification of the reactor structure is evaluated according to both the NRC 10CFR61 and Fetter waste disposal concentration limits. After 5.6 years of irradiation, the blanket will only qualify for Class C low level waste. After 30 years of operation, the shield will also qualify for disposal as Class C waste. Only remote maintenance will be allowed inside the containment building
Keywords :
fusion reactor blankets; fusion reactor design; fusion reactor safety; neutron activation analysis; radioactive waste; shielding; Class C low level waste; Fetter waste disposal concentration limits; PULSAR-II fusion power reactor; PULSAR-II pulsed tokamak power plant design; Tenelon; V-5Cr-5Ti alloy; activation analysis; blanket; containment building; integrated decay heat; liquid-Li cooling; low activation austenitic steel; radwaste classification; remote maintenance; shield; total decay heat; Activation analysis; Biological information theory; Biological system modeling; Fusion reactor design; Inductors; Lithium; Neutrons; Plasma confinement; Solid modeling; Tokamaks;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534392