ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
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CAYjMIUM FRACTION ' ~<br />
PERlOD ENDING SEPTEMBER JO, 7954<br />
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RADIAL DISTANCE f FWM CLNTER OF CURVE (In 1<br />
Fig. 4.3. Power Distribution of Mid-Plane of Reactor. The paired points on the bare aluminum foil<br />
activation curve nt 6.4,6.9, and 7.1 in. were obtained from foils placed on opposite sides of the same uro-<br />
nium foil.<br />
metals, such cis Inconel, nickel, and cadmium.<br />
Upon completion of the experiments on this as-<br />
sembly, it is planned to construct a larger reactor<br />
of the same shape that will consist of three regions,<br />
with the beryllium island and reflector separated<br />
by the fuel annulus. The diameters of the beryllium<br />
island and the fuel annulus will be about 10.4 and<br />
20 in., respectively. Initially, the assembly will<br />
have no structural materials, such as Inconel core<br />
shells, and it will provide a further check of the<br />
calculational methods.<br />
SUPERCRITICAL-WATER REACTOR<br />
J. S. Crudele J. W. Noaks<br />
Pratt and Whitney Aircraft Division<br />
The Supercritical-Water Reactor (SCWR) critical<br />
assembly was described previously4 as consisting<br />
of an aqueous solution of enriched UO,F, con-<br />
-<br />
*E. L. Zimmermon, J. S. Crudele, and J. W. Nooks,<br />
ANP Quar. Prog. Rep. Mar. IO, 1354, <strong>ORNL</strong>-1692, p 45.<br />
tained in stainless steel tubes distributed in an<br />
organic liquid in a pattern designed to give a uni-<br />
form radial thermal-neutron flux. The liquid, Furfural<br />
(C,H,O,), which also serves os c1 neutron reflector<br />
on the lateral surface of the cylindrical tube bundle,<br />
has a hydrogen density approximately the same as<br />
that of water under the temperature and pressure<br />
conditions designed for the SCWR, It simulates<br />
the nuclear properties of supercritical water as<br />
well as can be determined without further knowledge<br />
of the effect of binding energies on diffusion and<br />
slowing down lengths. Stainless steel was inserted<br />
in the fuel tubes to represent the reactor structure.<br />
The loading of the critical assembly was calcu-<br />
lated by Pratt & Whitney Aircraff Division person-<br />
nel,' by use of a four-group diffusion theory method,<br />
ta be 15.34 kg of U235 and 261 kg of stainless<br />
steel in CI 76.2-crn equilateral right cylinder with a<br />
'private conlrnunication from George Chase, Fox<br />
Project, Pratt S Whitney Aircraft Division.<br />
47