ORNL-1771 - Oak Ridge National Laboratory

15. LlST OF REPORTS ISSUED DURi G THE QUARTER
REPORT NO. TITLE OF REPORT AUTHOR DATE ISSUED
CF-54-7- 1 1
CF-54-7-143
CF-54-7- 144
CF-54-8-171
CF-54-6-201
CF-54-7-1
1. Aircraft Reactor Experiment
Fuel Activation Method for Power Determination of the ARE
ARE Operating Procedures, Part I, Pre-Nuclear Operation
ARE Operating Procedures, Part II, Nuclear Operotion
Critical Mass of the ARE Reactor
A Reactor Design Parameter Study
!I. General Design
The Effect of the RMR Shield Weight of Varying the Neutron
and Gamma Dose Components Taken by the Crew and
Camparison of the RMR Shield Weight to that for an Idealized
Shield
E. 6. Johnson
W. 6. Cottrell
J. L. Meem
C. B. Mills
CF-54-7- 187 Test Results and DesignCornporisons for Liquid Metal-to-Air H. J. Stumpf
Radiators
R. E. MacPherson
J. G. Gallagher
C F -54 -8-2 00 High Conductivity Fin Test Results
J. E. Ahern
CF-54-7-166
CF-54-8-199
CF-54 -7- 15 9
CF-54-8-180
111. Experimental Engineering
MorseSilent Chain Drive Test on ARE Pump Hat Shakedown
Test Stand
Aircraft Reactor Experiment Fual-Removal System Mockup
IV. Critical Experiments
The First Assembly of the Small Two-Region Reflector
Moderated Reactor
The Second Assembly of the Small TwwRegion Reflector
Moderated Reactor
V. Metallurgy
CF-54-8-2 7 Preliminary Metallographic Examination of K-25 Heat Exchanger
Loop
CF-54-6- 188
CF-54-7- 145
VI. Heat Transfer and Physical Properties
A. H. Fax et al.
R. M. Spencer
H. J. Sturnpf
A. G. Grindell
J. Y. Ertabrook
Dunlop Scott
Dunlap Scott
R. S. Craiise
G. M. Adamson
Physical Properfy Charts for Some Reactor Fuels, Coolants,
and Miscellaneous Materials (4th Edition)
S. 1. Cohen et nl.
Measurement of the Thermal Conductivity of Molten Fluoride W. D. Powers
Mixture No. 10-4
S. J. Claiborne
7-3 1-54
7-20-54
7-27-54
8-28-54
6-25-54
8-26-54
9-1 9-54
8-2 7-54
9- 16-54
8-26-54
9-26-54
8-26-54
8-5-54
6-21-54
8-24-54
183