THE PEBBLE BED REACTOR PROGRAM. Current Fuel Element Developments and Their Effects on the Pebble Bed Reactor Development Program (open access)

THE PEBBLE BED REACTOR PROGRAM. Current Fuel Element Developments and Their Effects on the Pebble Bed Reactor Development Program

Recent fuel element irradiations demonstrated the structural integrity of spherical uranium-graphite fuel elements at burn-ups in excess of the design requirements of a 125 Mw(e) Pebble Bed Reactor (PBR) power plant. Other irradiations indicated the successful development of a coated fuel particle which permits fabrication of fuel elements meeting the PBR design objectives of a fission-product release rate (R/B) ? /sup 10-6/. beta plus gamma system activity in a 125 Mw(e) PBR is 490 c, assuming complete release of /sup lO-6/ of all fission products volatile at or below 2500 deg F. The low R/B being obtained from PBR fuel elements indicates that decay during diffusion of the short-lived volatile precursors of nonvolatile daughter products will result in further reduction of this system activity, and an increase in the average half life of the fission products remaining in the system will increase the efficiency of a bypass clean-up system. The method of fabricating coated particles by the hydrolysis of metallic chlorides to produce oxides or pyrolysis of hydrocarbons to produce carbon on a suitable substrate, is described, and preirradiation test results are given. An accelerated coated-fuel-particle program is discussed as well as development work on the Pebble Bed REactor concept …
Date: May 10, 1960
Creator: unknown
System: The UNT Digital Library
Synthesis and Fabrication of Refractory Uranium Compounds. Monthly Progress Report No. 8 for April 1 Through April 31, 1960 (open access)

Synthesis and Fabrication of Refractory Uranium Compounds. Monthly Progress Report No. 8 for April 1 Through April 31, 1960

The effort on uranium silicide during the repent period was equally divided between synthesis and fabrication. The goal for the synthesizing effort was to make U/sub 3/8i/sub 2/ of higher purity than that made in the past, and the goal for the fabrication effort was to make pellets of density higher than 93%. Both goals were achieved. Experiments in simultaneous synthesis and fabrication of uranium monocarbide are reported in which mixtures of uranium powder and carbon were hot pressed. Sintering experiments on uranium monocarbide produced pellets of 91 to 91% theoretical density; however, cracking and oxidation were observed. Further experiments are planned in which oxidation will be reduced to a minimum. (J.R.D.)
Date: May 10, 1960
Creator: Taylor, K. M.; Lenie, C. A.; Doherty, P. E.; Hailey, L. N. & Keaty, T. J.
System: The UNT Digital Library
Design, Development, and Operation of Metal-Diaphragm Reactor-Service Pumps (open access)

Design, Development, and Operation of Metal-Diaphragm Reactor-Service Pumps

The design, development, and operation of metaldiaphragm service pumps for aqueous homogeneous reactojs are discussed. It is shown that with proper design and materials selection, the dlaphragm heads and check valves can operate continuously for about two years. (C.J.G.)
Date: May 10, 1960
Creator: Hise, E. C.
System: The UNT Digital Library