Evaluation study of the tritium-handling requirements of a Tokamak Experimental Power Reactor

Technical Report · Sat Nov 01 04:00:00 EST 1975

OSTI ID:4138929

Wittenberg, L J; Bixel, J C; Braun, J D; Hobrock, D L; Kershner, C J; Miles, J C; Rhinehammer, T B; Watkins, R A; Wilkes, W R

This report is a Mound Laboratory evaluation study of the tritium handling and containment technology common to all Tokamak Experimental Power Reactor (EPR) conceptual designs. The EPR is assumed to be fueled with a 50/50 deuterium-tritium mixture and to produce thermal power in the 150 to 450 MW range with mechanical power achieved by a steam turbine. The structure will be fabricated principally with stainless steel and no tritium breeding is anticipated during the initial operation. The necessary plant systems and associated administrative control requirements that are discussed include the plasma fuel and exhaust systems, the blanket and coolant system, the plant containment system, tritium accountability, and construction and operation of the reactor facility. (auth)

• Research Organization: Mound Lab., Miamisburg, Ohio (USA)
• DOE Contract Number: E(33-1)-GEN-53
• NSA Number: NSA-33-009076
• OSTI ID: 4138929
• Report Number(s): MLM--2259
• Country of Publication: United States
• Language: English

Related Subjects

*TOKAMAK DEVICES-- RADIATION HAZARDS
*TRITIUM-- RADIATION HAZARDS
700206* --Fusion Energy--Fusion Power Plant Technology-- Tritium Processing
Environment & Safety
CONSTRUCTION
DEUTERIUM
N70800* --Physics--Controlled Thermonuclear Research-- Thermonuclear Engineering & Equipment
OPERATION
SAFETY
STAINLESS STEELS
STEAM TURBINES