Serial/Series Title
11 Matching Results
Results open in a new window/tab.
Results:
1 - 11 of
11
HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3
ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) density pellets produced few fines. Approximately 5 hours were required to dissolve the UO/sub 2/ core material (14,000 Mwd/TU) in 4M HNO/sub 3/ versus 6 to 7 hours for unirradiated pellets to produce a solvent extraction feed of 100 g U/l and 3M HNO/sub 3/. Gamma decontamination factors for uranium in the Purex CU stream and plutonium in the BP stream were increased by factors of 2 to 10 from the normal 1.3 x 10/sup 3/ and 2.1 x 10/sup 3/, respectively, by pretreatment of the solvent extraction feed with dincetyl monoxime or its degradation product, oxalic acid. Preliminary data indicate radiation damage degrades the solvent, 30% TBP diluted with Amsco 125- 82, upon one pass through the mixer-settler banks with feed solutions irradiated …
Date:
May 14, 1962
Creator:
Goode, J.H. & Baillie, M.G.
System:
The UNT Digital Library
Stress Analysis of the PM-2A Reactor Vessel
The stress analysis performed on the PM-2A reactor vessel and cover is discussed. The maximum combined stress (51,000 psi) occurred in the studs after reaching steady-state conditions. A fatigue analysis indicated that this stress could be safely applied 2500 times, and since the studs do not approach 2500 cycles from initial stud tightening to steady-state conditions, they should not suffer any fatigue damage. (auth)
Date:
May 14, 1962
Creator:
Rowekamp, B. J.; McLaughlin, D. W.; Chittum, R. A. & Aitken, C. C.
System:
The UNT Digital Library
Reactor and Materials Technology monthly report, April 1965
This report details activities of the Reactor and Materials Technology Department during the month of April 1965.
Date:
May 14, 1965
Creator:
Albaugh, F. W.
System:
The UNT Digital Library
Pacific Northwest Laboratory monthly activities report, April 1965
This report discusses research at the Pacific Northwest Laboratory on topics relating to hanford production reactors. The topic deal with: reactor and material technology; reactor physics and instruments; chemistry; biology and medicine; applied mathematics; radiation protection; and test reactor and engineering services.
Date:
May 14, 1965
Creator:
unknown
System:
The UNT Digital Library
Project CLEER: A study of the heat transfer characteristics of a capillary wetted surface
An experimental program (Project Cleer) was initiated to investigate the heat transfer characteristics of a surface covered with a wick-like material and cooled by a capillary liquid. The preliminary heat transfer analyses developed and the measuring equipment and methods to be used are discussed. (LCL)
Date:
May 14, 1968
Creator:
Van Sant, J. H.
System:
The UNT Digital Library
Irradiation test, preliminary report
None
Date:
May 14, 1965
Creator:
unknown
System:
The UNT Digital Library
AN ACCURATE CURRENT INTEGRATOR IN THE RANGE OF 10$sup -5$ TO 10$sup -9$ AMPERES
None
Date:
May 14, 1965
Creator:
Law, L A & Weinstein, J
System:
The UNT Digital Library
THE TENSILE FRACTURE STRAIN OF GRAPHITE DETERMINED DURING NEUTRON IRRADIATION
None
Date:
May 14, 1965
Creator:
Jackson, J.L.
System:
The UNT Digital Library
Project Gasbuggy
From cover: "A feasibility study concerned with nuclear explosive stimulation of a natural gas reservoir, prepared by El Paso Natural Gas Company, the United States Atomic Energy Commission and the United States Bureau of Mines."
Date:
May 14, 1965
Creator:
unknown
System:
The UNT Digital Library
The Corrosion of Unalloyed and Alloyed Plutonium in Monobromobenzene and Freon-113 Fluorocarbon
None
Date:
May 14, 1965
Creator:
Dringman, M. R.
System:
The UNT Digital Library
SNAP-50 reactor development program
None
Date:
May 14, 1962
Creator:
unknown
System:
The UNT Digital Library