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Measurement of Xenon Poisoning in the HRT
Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date:
April 19, 1962
Creator:
Burch, W.D.
Object Type:
Report
System:
The UNT Digital Library
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures
Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E xperiment and analytical methods employed to interpret corrosion and masstransfer behavior in this reactor system are discussed. The products of corrosion of metals by fluoride melts are soluble in the molten salt; accordingly passivation is precluded and corrosion depends directly on the thermodynamic driving force of the corrosion reactions. Compatibility of the container metal and molten salt, therefore, demands the selection of salt constituents which are not appreciably reduced by useful structural alloys and the development of container materials whose components are in near thermodynamic equilibrium with the salt medium. Utilizing information gained in corrosion testing of commercial alloys and in fundamental interpretations of the corrosion process, an alloy development program was conducted to provide a high temperature container material that combined corrosion resistance with useful mechanical properties. The program …
Date:
September 19, 1962
Creator:
DeVan, J. H. & Evans, R. B., III
Object Type:
Report
System:
The UNT Digital Library
MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961
The Molten Salt Reactor Experiment design, component development, and engineering analysis is discussed. Materials studies for the Molten-Salt Reactor Program including metallurgy, in-pile tests, chemistry, engineering research, and fuel processing are described. (M.C.G.)
Date:
January 19, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
INSTRUMENTATION AND CONTROLS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JULY 1, 1961
The report comprises seven sections. A separate abstract was prepared for each section. (J.R.D.)
Date:
February 19, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Low Temperature Thermoluminescence of Gamma Irradiated Potassium Dihydrogen Phosphate
Thermoluminescence in potassium dihydrogen phosphate (KDP) induced by Co/ sup 60/ gamma irradiation at liquid nitrogen temperature (-198 deg C) was investigated. Glow curves in the temperature range --196 to 0 deg C were measured for a series of gamma exposure dosages ranging from 10/sup 4/ roentgen to 5 x 10/sup 6/ roentgen. The heating rate used for glow curve measurements was 12 deg C per minute. Twice recrystallized Mallinckrodt reagent grade potassium dihydrogen phosphate, with a grain size between 100 and 170 mesh, was used for most samples. In the case of the powder samples, the glow curve for an exposure dose of 10/sup 4/ roentgen exhibited two peaks in this temperature range, one at approximately --78 deg C and the other at approximately -146 deg C. The -78 deg C peak split into two distinct peaks with increasing dosage. At still higher doses an additional peak at about -9 deg C became evident. This peak may, however, be due to aluminum oxide. Calculation of the trap depth, E, and the frequency factor, s, associated with the --78 deg C peak, by the approximate method of Grossweiner yielded values of 0.485 ev and 9.97 x 10/sup 10/ sec/sup -1/ …
Date:
October 19, 1962
Creator:
Sims, T. M.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Gcr-Orr Loop No. 2 Filter Tests. Part Ii
Tests of Cambridge absolute filters, Model Sl-071, specified for use in the GCR-ORR Loop No. 2 as full-flow, primary coolant fiiters were completed. kD.O.P/ (dioctylphthalate) efficiency tests were performed on three filters in the as-received condition, on two filters following canning and thermal cycling, and on one of the canned fiIters following bsking out. None of the three units met the design criteria of 99.97% efficiency for removal of 0.3 micron particles in the as-received condition. The postthermal cycle efficiencies of the canned fiIters were slightly higher than their respective as-received efficiencies. At the corapletion of testing, the two fiiters canned for installation in the reactor facility had measured efficiencies of 99.855% and 99.93%. These values were judged acceptable for the intended application/su The thermal cycling of the two canned filters and the subsequent baking out of one of these units demonstrated that a limited amount of off-gas products would be given off/su Pressure drop tests were performed on the canned fiiters with instrument air (ambient temperature, atmospheric pressure) over a flow rate range of 150 to 530 lb/hr. Curves of pressure drop across each fiIter versus Reynolds number were plotted for air and He. (auth)
Date:
February 19, 1962
Creator:
Flint, F. A. & Smith, A. M.
Object Type:
Report
System:
The UNT Digital Library
An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-Aluminum Alloy Research Reactor Fuel Plates
Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding. This diffusion is likely because of the 600 deg C heat treatments used in the conventional fabrication process. Uranium determinations based on neutron activation analysis of machined layers from fuel plate surfaces showed that rolling-mill equipment, contaminated with highly enriched uranium, was responsible for transferring as much as 180 ppm U to plate surfaces. By careful practice where cleanliness is emphasized, surface contamination can be reduced to 0.6 ppm U/sup 235/. The residue remaining on the plate surface may be accounted for by diffusion of uranium from the fuel alloy into and through the cladding of the fuel plate. Data obtained from preliminary diffusion studies permitted a good estimate to be made of the diffusion coefficient of uranium into aluminum at 600 deg C: 2.5 x 10/sup -8/ cm//sec. To …
Date:
March 19, 1962
Creator:
Beaver, R. J.; Erwin, J. H. & Mateer, R. S.
Object Type:
Report
System:
The UNT Digital Library
SM-1 Reactor Vessel Cover and Flange Stress Analysis
The maximum stress calculated for the SMl-1 reactor vessel closure studs occurs during operation at full power. This value is 27,180 psi of which 19,800 psi is tension and 7380 psi bending. This stress does not include a stress concentration factor for effect of threads. It was eonservatively assumed the studs were initially tightened to a code allowable stress of 20,000 psi as specified in the ASME Code rather than the lesser stress obtained by the normal operating procedure. The maximum calculated stress occurs at the outside surface of the cover where the stress ranges from 318 psi in tension to 90,660 psi in compression. The alternating stress is 50,000 psi. According to the Navy Code for a stress range of 50,000 psi, the eover material ean safely undergo a maximum of 1600 cycles. It was estimated that the SM-1 will go through approximately 000 startup and shutdown cycles during a 20-yr life period, so the calculated stress is regarded as safe. For a transient eondition of 30 deg F/hr during heat-up, approximate temperature differences between the inside and outside surfaces of the cover were obtained. Temperature differentials between the inside and outside surfaces of the cover are increased by …
Date:
February 19, 1962
Creator:
Sayre, M. F.
Object Type:
Report
System:
The UNT Digital Library
PREPARATION AND FABRICATION OF ThO$sub 2$ FUELS
Dense partricles of ThO/sub 2/-UO/sub 2/ were prepared by a sol-gel process and vibratorily compacted into metal tubes to a density approaching 9.0 g/ cc. The steps in this method are all simple and can be carried out behind shielding, which is necessary for refabricating U/sup 233/ fuels. The sol-gel process consists of preparing a hydrous thoria sol, adding the U/sup 233/ as nitrate solution, evaporating to a gel, and finally calcining to almost theoretically dense oxide particles at orly 1150 deg C. The sol-gel-prepared oxide, after being sized, was compacted with a simple, inexpensive pneumatic vibrator. (auth)
Date:
June 19, 1962
Creator:
Ferguson, D.E.; Arnold, E.D.; Ernst, W.S. Jr. & Dean, O.C.
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report No. 13
Research was continued during the report period on the use of isotope neutron sources for producing short-lived radioisotopes. Experiments with a newly constructed betacounting cell are reported in which a 50-curie Be--Po neutron source was used. Study of the radiation chemistry of polymers was continued concerning the effects of polymer structure on free-radical formation. Free-radical formation in several additional polymers was studied. Preliminary work is also reported in an investigation of internal irradiation effects on the chemical activity of catalysts. (J.R.D.)
Date:
July 19, 1962
Creator:
Sunderman, D.N. ed.
Object Type:
Report
System:
The UNT Digital Library
[Photograph 2012.201.B0412.0048]
Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Classroom" for Mrs. Estelle Faulconer, Frederick Teacher, was the United Nations"
Date:
August 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0316.0722]
Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Larry Osterhout, 12, gets around in a mode of transportation popular 50 years ago"
Date:
July 19, 1962
Creator:
Garner, Frank
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0290.0142]
Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Seattle-bound with 90 of their original 99 silver dollars are Mr. and Mrs. L. J. Dancey, a Tennessee couple in Oklahoma City Thursday."
Date:
July 19, 1962
Creator:
Matheson, Mandell
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0366.0158]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "Sunday closing laws may come and go, but some work must continue tight through the seventh day."
Date:
January 19, 1962
Creator:
Matheson, Mandell
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0320.0215]
Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "is Tim Edwards, Kansas Highway Patrol trooper after he captured man and girl sought in shooting death of City Marshal Al Claycamp."
Date:
July 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0053.0275]
Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "Back yard of Mrs. Al Ackley suddenly was full of wrecked freight cars in Woodward Monday"
Date:
February 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0312.0069]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "Unusual collection of antique dolls is being used by Mrs. Margaret Boyt, Drumright bus station manager, as a basis for having an open house benefit for the new Drumright hospital"
Date:
October 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Board of Regents Board Meeting, 1962]
Photograph of the Board of Regents during a board meeting in 1962.
Date:
March 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Board of Regents Board Meeting (2), 1962]
Photograph of the Board of Regents during a board meeting in 1962.
Date:
March 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Board of Regents Board Meeting (3), 1962]
Photograph of the Board of Regents during a board meeting in 1962.
Date:
March 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Board of Regents Board Meeting (4), 1962]
Photograph of the Board of Regents during a board meeting in 1962.
Date:
March 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Four Regents (2), 1962]
Photograph of Regents from the Board of Regents in 1962. There are four individual men dressed in suits.
Date:
March 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Four Regents, 1962]
Photograph of Regents from the Board of Regents in 1962. There are four individual men dressed in suits.
Date:
March 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The UNT Digital Library
[Photograph 2012.201.B0053.0276]
Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "Wreckage piled on the Santa Fe tracks at Woodward Monday when an eastbound Santa Fe train was derailed. The lead car of the 36 derailed freight cars, many loaded with potash, stopped about 10 feet short of the Al Ackley home near the right of way."
Date:
February 19, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History