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Defect testing of coextruded uranium-zircaloy-II clad fuel material in a 300 C out-of-reactor recirculating water loop: Interim report
A major problem in the development of a pressurized water reactor coolant system for the NPS is the rupture performance of the fuel elements. As water temperatures are increased to 300 C, uranium corrosion rates increase rapidly. Swelling of the uranium fuel by corrosion could cause the process tube to burst or reduce the tube cooling water flow below acceptable limits. The desirability of slow cooling of the water to avoid thermal shocks to the reactor piping after a rupture is detected further complicates discharge and decontamination problems as fuel will continue to corrode with attendant fuel element damage during the cooling period. Coextruded uranium-zircaloy-2 clad fuel elements are scheduled for use in the NPR. The rupture behavior of this type fuel material after heat treatment was studied in ELMO-4, an out-of-reactor recirculating water loop. Several types of initial defects were studied. Fuel materials with five different heat treatment histories and with different types of defects were tested to determine their rupture behaviors. The five conditions were (1) as-extruded material as received from Nuclear Metals, Inc., (2) beta heat-treated and water quenched, (3) beta heat-treated and air-cooled, (4) beta heat-treated, isothermally treated at 600 C and air-cooled, and (5) beta …
Date:
September 25, 1959
Creator:
Hayden, K. D. & Goffard, J. W.
System:
The UNT Digital Library
Specifications: Laboratory hot press process for {open_quotes}C{close_quotes}size I & E fuel elements
Hot press canning of internally and externally cooled fuel elements has been developed to a point where the process is feasible. Complete specifications have been written for the process covering component, dies and punches, furnace construction, nickel plating, component cleaning, component assembly, sizing, hot pressing and inspection. Drawings covering each major item are included.
Date:
September 25, 1959
Creator:
Tverberg, J. C.
System:
The UNT Digital Library
The Constitution of Delta-Phase Alloys of the System Uranium-Molybdenum-Titanium
None
Date:
September 25, 1956
Creator:
Saller, H. A.; Rough, F. A.; Bauer, A. A. & Doig, J. R.
System:
The UNT Digital Library
Nuclear Gas Engine
A preliminary design study of the nuclear gas engine, consisting of a gas-cooled reactor directly coupled to a reciprocating engine, is presented. The principles of operation of the proposed gas engine are outlined and typical variations anre discussed. The nuclear gas engine is compared with other reciprocating engines and air compressors. A comparison between the ideal and actual cycles is made, with particular attention given to pumping, heat, and other losses to be expected. The applications and development of the nuclear gas engine are discussed. (W.D.M.)
Date:
September 25, 1958
Creator:
Fraas, A. P.
System:
The UNT Digital Library
WHY SEPARATE STABLE ISOTOPES
None
Date:
September 25, 1950
Creator:
Keim, C.P.
System:
The UNT Digital Library
THE ELECTRICAL PROPERTIES OF URANIUM OXIDES
None
Date:
September 25, 1956
Creator:
Willardson, R.K.; Moody, J.W. & Goering, H.L.
System:
The UNT Digital Library
Preliminary Outline of the Critical Assembly and Initial Operational Testing of L-3 Reactor
None
Date:
September 25, 1953
Creator:
Remley, M. E.
System:
The UNT Digital Library
Recommended settings for 105-C trips
This memorandum discusses the engineered safety system which combines the Ball 3-X System with the VSR System. The operation of the system is detailed and settings are recommended for 105-C trips.
Date:
September 25, 1952
Creator:
Roy, G. M.
System:
The UNT Digital Library
Summer Quarter, 1958, Co-Op Report
process and fluidized bed reactor is reported. Work done on cleanup of mercury from the Metallex process is also described. (J.R.D.)
Date:
September 25, 1958
Creator:
Smith, M. O.
System:
The UNT Digital Library