PROGRESS REPORT ON PEBBLE BED REACTOR PROGRAM FOR PERIOD JUNE 1, 1959- OCTOBER 31, 1960

Technical Report · Tue Oct 31 04:00:00 EST 1961

OSTI ID:4838072

A description is given of analytical and development work in connection with the Pebble Bed Reactor concept. The principle involved in the reactor is the heating of graphite pebbles by the fission of contained uranium and transfer of the heat generated to helium which is circulated through the permeable bed. Fuel elements are being developed for the Pebble Bed Reactor which, based on irradiation results to date, are extremely effective in retarding the release of gaseous fission products. The effects of core materials as dictated by this development are appraised as well as the effects of local voidage caused by the core containing wall and other fixed graphite. A parametric survey was made of the nuclear and thermal characteristics of a series of cores using a modified two- group, two-region model developed for this purpose. An IBM 650 program was developed to handle this modified two-group model, which program was used in the parametrtc study. System activity was re-evaluated in light of information resulting from the Fuel Cycle Development Program. The use of an ultra- centrifuge to concentrate gaseous fission products to facilitate their removal from the system was investigated. Design principles were established for a continuous flow charcoal adsorber. A diffusion separation cell was sized, based on existing design data, for removal of fission products and contaminants. Experimental work was done on fuel loading patterns and the fiow of balls through the bed. Ball bed friction factors were established over a range of Reynolds numbers from 5,000 to 50,000, and entrance and exit effects and surface roughness of fuel elements evaluated. Experimental work was done to determine if the thermal growth of the bed would result in fuel element failure. A mathematical model was developed to account for both radial and axial flow through the core resulting from its three-dimensional nature. Flow perturbations resulting from core hot spots were investigated using an IBM 650 program developed espectally for this mathematical model. Further development programs for the Pebble Bed Reactor concept and gas cycle reactors in general are discussed. (auth)

• Research Organization: Sanderson and Porter, New York
• NSA Number: NSA-15-028816
• OSTI ID: 4838072
• Report Number(s): NYO-9071
• Country of Publication: United States
• Language: English

Related Subjects

ACTIVATED CARBON
ADSORPTION
CENTRIFUGATION
COMPUTERS
CONTAMINATION
DECONTAMINATION
DIFFERENTIAL EQUATIONS
DIFFUSION
DISTRIBUTION
EXPANSION
FAILURES
FISSION PRODUCTS
FLUID FLOW
FRICTION
FUEL ELEMENTS
FUELS
GAS COOLANT
GAS FLOW
GASES
GRAPHITE MODERATOR
GROUP THEORY
HEAT TRANSFER
HELIUM
PEBBLE BED
PELLETS
PROGRAMMING
REACTOR CORE
REACTOR FUELING
REACTOR TECHNOLOGY
REACTORS
SEPARATION PROCESSES
SURFACES
URANIUM
ZONES