Serial/Series Title
Proceedings of the Workshop on Geothermal Reservoir Engineering
11
Fiscal Year 2000
3
Carbon Sequestration on Surface Mine Lands Quarterly Report
2
Downhole Power Generation and Wireless Communications for Intelligent Completions Applications, Quarterly Report
2
Federal Emergency Management Information System (FEMIS)
2
Fiscal Year 1990
2
Fiscal Year 1999
2
Fiscal Year 2001
2
Improved Miscible Nitrogen Flood Performance Utilizing Advanced Reservoir Characterization and Horizontal Laterals in a Class I Reservoir - East Binger (Marchand) Unit Quarterly Report
2
Low-Cost Solar Array Project
2
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SHUTDOWN AND STARTUP PROCEDURE FOR HRR
None
Date:
July 24, 1956
Creator:
Michelson, C.
Object Type:
Report
System:
The UNT Digital Library
EXAMINATION OF TITANIUM PULSE FEEDER DIAPHRAGM FAILURE
A Ti pulse feeder diaphragm failed by cracking after 450 hr service in the Homogeneous Reactor Test mock-up. The diaphragm, which was made of MST Grade III Ti, was vibrated at 78 cpm at 40 to 50 deg C. One side of the diaphragnn was exposed to demineralized H/sub 2/O and the other side was exposed to 10g U/l UO/ sub 2/SO/sub 4/ solution. The main corrosion product was TiO/sub 2/. (W.L.H.)
Date:
August 24, 1956
Creator:
Kegley, T.M. Jr.
Object Type:
Report
System:
The UNT Digital Library
HAZARD TO HRT CONTAINMENT CELL FROM ZIRCONIUM-WATER REACTION OF D$sub 2$ EXPLOSION
None
Date:
August 24, 1956
Creator:
Rosenthal, M.W.
Object Type:
Report
System:
The UNT Digital Library
Hot Semiworks summary: Run PX-13
This report provides a summary of the Hot Semiworks Unit Run PX-13. During Run PX-12 acceptable HA Column decontamination was demonstrated; however, generally under unstable column operating conditions. The principal objectives of PX-13 were: To duplicate the high PX-12 decontamination factors under stable HA Column operating conditions; to study the effects of fresh solvent, IO Column CP carbonate washed solvent, and IO Column Technical grade carbonate washed solvent on A Column decontamination factors; to study the effect of increasing the HA, HC, and IA uranium processing rates to 14 tons per day (plant equivalent); to study the effect of an intermediate 2A Column scrub on UX{sub 1} decontamination; and to study the effect of sulfamic acid addition to the HAF, HAS, IAF, and IAS and NaNO{sub 2} omission from the HAF and IAF.
Date:
August 24, 1956
Creator:
Siegler, M. & Oberg, G. C.
Object Type:
Report
System:
The UNT Digital Library
Infrared Program of the ORNL Spectroscopy Research Laboratory
None
Date:
August 24, 1956
Creator:
Morgan, H. W.; Staats, P. A.; Goldstein, J. H. & McNally, J. R., Jr.
Object Type:
Report
System:
The UNT Digital Library
RESONANCE ABSORPTION OF NEUTRONS. CHAPTER 2. DOPPLER EFFECT IN AN INFINITE HOMOGENEOUS MEDIUM
None
Date:
August 24, 1956
Creator:
Dresner, L.
Object Type:
Report
System:
The UNT Digital Library
Thorex: Second Thorium Cycle Manpower and Cost Summary
None
Date:
September 24, 1956
Creator:
Winsbro, W. R. & Bottenfield, B. F.
Object Type:
Report
System:
The UNT Digital Library
Plasma Confinement at Uniform Temperature
None
Date:
October 24, 1956
Creator:
Woods, C. H.
Object Type:
Report
System:
The UNT Digital Library
Relations and Utilities Operation monthly report, September, 1956
This document contains the September 1956 management and operations statistics of the Hanford Atomic Products Operation (HAPO) for their ``Relations and Utilities Operations.`` This is a monthly report. (BN)
Date:
October 24, 1956
Creator:
Johnson, D. M.
Object Type:
Report
System:
The UNT Digital Library
C-Reactor I and E loading instability limits
The pilot charging of I & E fuel elements has been implemented at C-Reactor under Production Test IP-19-A. It was necessary to provide adequate tube protection against flow interruption by establishing proper trip setting on the Panellit pressure gauges. the administration of these Panellit trip settings is done by trip-before- boiling tube outlet temperature limits, which are similar in principle to the current instability limits. Trip-before-boiling limits for C-Reactor I & E fuel elements loadings are presented in this document.
Date:
January 24, 1957
Creator:
Hess, K. W.
Object Type:
Report
System:
The UNT Digital Library
ESTIMATED GAMMA RADIATION LEVELS AT ACCESS HOLES IN THE HRT SHIELDING
None
Date:
January 24, 1957
Creator:
Collins, C.W.
Object Type:
Report
System:
The UNT Digital Library
REACTOR COOLANT PUMPS: SODIUM FREEZE SEAL COOLING LOADS
>A summary of the cooling load data for the SRE sodium coolant pump freeze seals is presented. (J.R.D.)
Date:
January 24, 1957
Creator:
Atz, R.W.
Object Type:
Report
System:
The UNT Digital Library
Secondary Refrigerant for HRT Refrigeration System
None
Date:
January 24, 1957
Creator:
Robertson, R. C. & McLain, H. A.
Object Type:
Report
System:
The UNT Digital Library
HAZARDS SUMMARY REPORT ON CRITICAL EXPERIMENT PROGRAM NO. 1 AT CANEL
The construction of a critical assembly is proposed for determining the characteristics of the PWAC Na-cooled, heterogeneous aircraft reactor design. The experimental facility would be located at the CANEL site. The site meteorology, hydrology, geology, and topography are considered; the facility and critical assembly design is shown, and the extent of hazards from accidents and sabotage is evaluated. (D.E.B.)
Date:
May 24, 1957
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Interim report on tests simulating the transient response of individual process tubes to inadvertent plugging
Current Panellit protection procedures, termed instability limits, come from calculations based on steady state experiments. However, the actual conditions in a process tube following a plugging occurrence sufficient to cause unstable flow are transient rather than steady state, and cannot be determined with great precision except by transient state experimentation. As a result, a program was initiated by the thermal Hydraulics Operation of HLO to perform a series of transient heat transfer experiments which would define the process tube response to (1) rapid plugging in the process tube assembly, (2) slow plugging in the process tube assembly, and (3) power excursions above normal of varying amounts. Transient heat transfer experimentation on a large scale is not common and many difficulties have been encountered. After preliminary runs were made and reported, a further series of runs were planned and run which would include K as well as BDF type data and would define more closely the upper limit of the panellit protection. During the test runs, data from these transient experiments are recorded on high speed recording instruments, each of which has a calibration which is subject to change regardless of the efforts expended by the experimenters. This means that checking …
Date:
May 24, 1957
Creator:
Batch, J. M.; Hesson, G. M.; Thorne, W. L. & Toyoda, K. G.
Object Type:
Report
System:
The UNT Digital Library
DETERMINATION OF TRACE AMOUNTS OF SULFUR IN FLUORIDE SALTS
None
Date:
June 24, 1957
Creator:
Gilbert, T.W. & White, J.C.
Object Type:
Report
System:
The UNT Digital Library
The Effectiveness of Control-Rod Materials
None
Date:
June 24, 1957
Creator:
Redmond, R. F. & Dayton, R. W.
Object Type:
Report
System:
The UNT Digital Library
RADIOACTIVE WASTE DISPOSAL SYSTEM
Seven illustrations are given for convenience in develop-ing operating procedures for disposal of PWR wastes. The illustrations include radioactive waste disposal systems for service building wastes, liquid effluents, solid and gaseous wastes, cooling water, steam system, and miscellaneous service lines. (J.E.D.)
Date:
July 24, 1957
Creator:
LaPointe, J.R.
Object Type:
Report
System:
The UNT Digital Library
Reduction and Stabilization of Plutonium Nitrate in Cation Exchange Feed and Product Solutions
In the conceutration and purification of Pu by cation exchange, the feed solution must be in the plus three valence state, but the nitrate solution from a solvent extraction process contains a high% of Pu/sup 4+/ and a small amount of Pu/sup 6+/. It was desired to find a reducing agent satisfactory for the reduction of Pu/sup 4+/ and Pu/sup 6+/ in Purex product streams and to make these streams suitable as cation exchange feed. The bisulfates met the requirements for speed and completeness of reduction in the feed material. (J.E.D.)
Date:
September 24, 1957
Creator:
Brunstad, A. & Smith, R. C.
Object Type:
Report
System:
The UNT Digital Library
BEVATRON OPERATION AND DEVELOPMENT. XIV. Period covered May, June, July 1957
The first half of this quarter was in part a continuation of the shutdown of the last period and in part a shutdown recovery period. The second half of the quarter was devoted to high-energy physics and chemistry research and to the extension and improvement in techniques of producing secondary-particle beams. The principal physics research efforts were a continuation of the investigations of interactions of negative particles in hydrogen using the 10- inch liquid hydrogen bubble chamber; counter sludies of the pi /sup 0/ modes of heavy-meson and hyperon decay; and a series of twenty-one nuclear emulsion exposures to K-meson beams. During this period twenty emulsion stacks were exposed for thirteen external groups. Thirteen target bombardments were made for the chemistry group. (For preceding period see UCRJ-8021.) (M. H.R.)
Date:
October 24, 1957
Creator:
Hartsough, Walter D.
Object Type:
Report
System:
The UNT Digital Library
PROPOSAL FOR INSTALLATION OF EQUIPMENT FOR TREATMENT OF ORNL HIGH LEVEL WASTE
It is proposed that neutralized ORNL storage tank supernate waste be used as a feed for a waste processing development facility. An electrolytic cell can be installed to remove nitrate and ruthenium from the wastes prior to discharge to the soil disposal pits. This eliminates the hazards of nitrate and ruthenium in the ORNL soil disposal pits. In addition, a continuous ion exchange unit can be installed to study the isolation of fission products from a portion of the waste stream. The total waste stream can be processed by the ion exchange if desired. A six to eight inch diameter continuous ion exchange contactor is considered sufficient to remove cesium, strontium, and rare earths from 5,000 to 10,000 gallons of waste per day. The estimated installed cost of such a unit is about ,000. The labor and chemical operating cost at 100% overhead is estimated at .50 per day. Three types of electrolytic cells were considered. All of the cells remove about 90% of the ruthenium by plating on the cathode. It is expected that the degree of ruthenium removed may be increased by further laboratory development. The first cell type is the Ionics cell which converts NaNO/sub 3/ to …
Date:
October 24, 1957
Creator:
Higgins, I.R.
Object Type:
Report
System:
The UNT Digital Library
ZIRCEX URANIUM SUBLIMATE LOSS
One of the limitations of the Zircex Process is the large percentage loss of U which is carried off with the volatile ZrCl/sub 4/. Since the ratio of U to Zr in the fuel element is quite small (< 1%), a large percentage of U loss can be caused by small amounts of U in the ZrCl/sub 4/ sublimate. The U loss must be kept below 1% if the Zircex Process is to be adapted to industrial scale processing. (W.L.H.)
Date:
January 24, 1958
Creator:
Jaworowski, T.R. & King, C.J. III
Object Type:
Report
System:
The UNT Digital Library
PHASE I--FOREIGN REACTOR FUEL SAMPLE IRRADIATION. IRRADIATION REQUEST ORNL- MTR-35
A series of im-pile fuel sample irradiation experiments was initiated to obtaim radiation damage information on fuel material combinations applicable to Foreign Reactor Program Fuel Elements where U/sup 235/ enrichment is limited to 20%. The series of expcriments will be divided into several phases, each being based on the materials combination employed. This report describes Phase I of the program which consists of determining the integrity and suitability of a 48 wt.% U--3 wt.% Si-49 wt.% Al alloy as a fuel for Foreign Reactor Fuel Elements. (auth)
Date:
February 24, 1958
Creator:
Leitten, C.F. & Thurber, W.C.
Object Type:
Report
System:
The UNT Digital Library
Stress Analysis of the Omr Core Vessel Support Structure
Studies were made to determine the stress equations necessary for the design and analysis of the OMR Core Vessel Support Structure. A parameter study of these equations applicable to the present core vessel design was also made. (W.L.H.)
Date:
February 24, 1958
Creator:
Peinado, C.
Object Type:
Report
System:
The UNT Digital Library