Design summary report of LCRE secondary coolant pump and sump /

"Contract AT(30-1)-2789."

Final report : LCRE valve development /

"Contract AT(30-1)-2789."

Increasing water filtration at Hanford /

"Contract No. AT(45-1)-1350."

Failure data handbook for nuclear power facilities : a guide for the design, construction, and maintenance of nuclear power plants from a reliability improvement standpoint /

Photocopy.

Proceedings of the Sodium Components Information Meeting held in Palo Alto, California, August 20-21, 1963 /

"Work performed under Contract No. AT(04-3)-189."

Experimental results of forced convection boiling potassium heat transfer and pressure drop tests /

"Contract AT(30-1)-2789."

Proceedings of the Japan-U.S. Seminar on HTGR Safety Technology, September 15-16, 1977, Brookhaven National Laboratory, Upton, N. Y. /

"NUREG/CR-0358, BNL-NUREG-50689, NRC-8"

The liquid metal fast breeder reactor programm, past, present, and future : report to the Congress /

"RED-75-352."

Proceedings of the Third Japan-U.S. Seminar on HTGR Safety Technology, June 2-3, 1982, Brookhaven National Laboratory, Upton, New York 11973 /

Includes bibliographical references.

Studies of a Self Cooled Lead Lithium blanket for HiPER Reactor

Within the frame of the HiPER reactor, we propose and study a Self Cooled Lead Lithium blanket with two different cooling arrangements of the system First Wall – Blanket for the HiPER reactor: Integrated First Wall Blanket and Separated First Wall Blanket. We compare the two arrangements in terms of power cycle efficiency, operation flexibility in out-off-normal situations and proper cooling and acceptable corrosion. The Separated First Wall Blanket arrangement is superior in all of them, and it is selected as the advantageous proposal for the HiPER reactor blanket. However, it still has to be improved from the standpoint of proper cooling and corrosion rates

Self Cooled Lead Lithium blanket and reactor for HiPER

Within the frame of the HiPER reactor, we propose and study a Self Cooled Lead Lithium blanket with two different cooling arrangements of the system First Wall – Blanket for the HiPER reactor: Integrated First Wall Blanket and Separated First Wall Blanket. We compare the two arrangements in terms of power cycle efficiency, operation flexibility in out-off-normal situations and proper cooling and acceptable corrosion. The Separated First Wall Blanket arrangement is superior in all of them, and it is selected as the advantageous proposal for the HiPER reactor blanket. However, it still has to be improved from the standpoint of proper cooling and corrosion rates