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H4LM Graphite
Control Design Review of P&W Quarterly for July-September, 1960
Tensile and stress rupture tests of S8DR Hastelloy-N heats: ORNL verification tests
Results of aquifer tests at hydrologic test sites 1 and 2, Tatum Dome, Lamar County, Mississippi
Logs of exploratory holes 2 and 7, Tatum dome, Lamar County, Mississippi. Technical letter: Dribble-16
The Preparation and Irradiation Behavior of Chemically-Nickel Plated Aluminum-Jacketed Fuel Elements
Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report
Finished Fuel and Target Dimensions
Xenon and Samarium reactivity effects associated with coolant loss
Loading and operating conditions for PT-IP-401-A and PT-IP-363-A in KER-1
GETR graphite irradiation capsules: H-4, 5, 6 equivalent N Reactor exposure
Hanford contribution for the eighteenth high temperature fuels committee meeting, May 19--21, 1964
Increased coolant flow H Reactor: PITA IP-27-I, Part 1. Supplement A
Qualitative aspects of neutron moderation with respect to graphite damage
Progress report for the projection welded brazed closure
Development Test IP-556-D, supplement A, irradiation service request HAPO-278 outgassing rate of tritium at high temperature
Fabrication of hot die sized Diffusion Bonded Fuel Elements for Supplement ``A`` to Production Test IP-546-A
C-Reactor graphite burnout interim report, 1P-25A(PT-105-532-E)
Post-irradiation measurements of PT-546 fuel elements
Status of development work on the hot die size fuel element growth problem
May 1969 COPE studies
Radiochemistry for the rupture of a Zircaloy-2 clad, natural uranium thermocouple fuel element in KER-1
Report to the FEDC working committee for the period September 1965--January 1966
Results of production test IP-528-I, Supplement A: B and D Reactors` high tank drawdown test
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