Heating calculations of fusion blanket experiments in a fission reactor
It has been proposed that testing fusion first wall/blanket/shield (FW/B/S) components in a fission reactor could provide timely solutions to some engineering problems that should be solved before the next generation of fusion reactors such as FED and INTOR can be built and operated reliably. It was earlier demonstrated that bulk heating rates in fusion FW/B/S could be simulated in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory thus making integral thermal-hydraulic and cooling systems testing feasible in certain existing fission reactors. This paper extends these results by describing the calculations in some detail and comparing the neutronics of the tokamak FW/B/S with the same system in the ETR.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6328848
- Report Number(s):
- DOE/ID/01570-T22; ON: DE81026020
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BARYON REACTIONS
BREEDING BLANKETS
FIRST WALL
HADRON REACTIONS
HEATING
MATERIALS TESTING
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIATION HEATING
REACTOR COMPONENTS
SHIELDING
SIMULATION
TEST FACILITIES
TESTING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS