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REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR MARCH 1, 1953 THROUGH MAY 31, 1953

Description: Power Breeder Reactor. Conceptual design studies for the Power Breeder Reactor indicate the feasibility of a contained primary coolant system in a package arrangement. One- and two-group calculations are presented in detail for preliminary PBR estimations. A technique for impregnating UO/sub 2/ with NaK has been developed. The resulting putty-type fuel was successfully extruded tbrough a 3/8-in. hole. Data are presented on the fuel element design factors imposed by heat transfer and cooling lim… more
Date: June 15, 1953
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monthly Progress Report for the Period September 1 to 30, 1958

Description: A 95-inch experimental Yankee sub-assembly was successfully brazed at 1890 plus or minus 10 for three hours then furnace cooled. All of the joints, outside ferrules, and control rod rubbing strips showed a brazed flllet. Dimensional surveys and joint strength studies indicate that two brazing techniques appear feasible for subassemblies. Codings for computers for use in core design problems are described. A series of criticality calculations for the three water-to-metal volume ratios of the Yan… more
Date: October 31, 1959
Creator: Garbe, R. W. & Walchli, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REACTOR PROJECTS BRANCH QUARTERLY PROGRESS REPORT FOR JULY, AUGUST, SEPTEMBER 1957

Description: Spert--I-- A brief resume of A'' core experiments is presented and the results of some of the static measurements with the B'' core are shown. It was found that four usable cores are possible with the removable-plate B'' fuel assemblies. The measurements made to date have been with a 24 fuel plate/ assembly, 32 assembly core, and include rod worth, flux distribution, temperature coefficient and preliminary void coefficient studies. Spert--II-- The construction contract was let amd construction … more
Date: October 1, 1957
Creator: Bright, G.O. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HIGH THERMAL-NEUTRON FLUX FROM FISSION OVER-SIMPLIFIED CASES

Description: Two simplified models are discussed in order to gain insight into the problems of a flux-trap reactor. The first model consists of source of fission neutrons, embedded into D/sub 2/O, Be, BeO, or C moderator, or a moderator of zero absorption cross section. The source is assumed not to absorb amy neutrons. This model gives five to eight times the thermal flux obtainable at the center of the fluxtrap reactor. The other model is a flux-trap reactor idealized by neglectimg all absorption in the mo… more
Date: February 26, 1958
Creator: Ergen, W.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. First Quarterly Progress Report, April 1-June 30, 1962

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. The feasibility of U/ sup 235/ coated solid state detectors for use in these measurements is being studied. A theoretlcal investigation is also in progress on the effects of a multi-region assembly on the fundamental… more
Date: July 1, 1962
Creator: Meyer, Paul & Garelis, Edwin
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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INTEGRAL NEUTRON THERMALIZATION. Annual Summary Report, October 1, 1961- September 30, 1962

Description: 3 3 9 9 7 6 : < 6 9 9 4 9 7 pulse of within a factor of two of the highest now available; operation was more than satisfactory. A pressure vessel to be used with the linac to measure neutron spectra of poisoned solutions for moderator temperatures up to about 600 l F was constructed. A 150-kv positive-ion accelerator was added to the linac facility to produce 2.5 and 14-Mev neutrons from T(d,n) and d(d,n) reactions. The 14-Mev neutron yield is about 10/sup 11/ neutrons/sec. Facilities for measu… more
Date: October 31, 1963
Creator: Beyster, J. R.; Brown, J. R. & Honeck, H. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Progress Report for the Period April 1, 1958 to June 30, 1958

Description: The principle progess during the second quarter of 1958 consisted of: accelerating the planning, scheduling, and coordination of the process-water and in-pile test loop irradiation programs; performing two-enrichment non-cycled core studies to determine the improvement in the radial hot channel factor over that which would apply for a uniform core; recalculating the contribution of control to the temperature coefficient using better thermal constant values and an improved method of obtaining co… more
Date: July 30, 1958
Creator: Coen, I. H. & Garbe, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GCRE Critical-Assembly Studies

Description: Critical-assembly studies were made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiment-1 (GCRE-l). Measurements of critical mass, flux and power distributions, and shutdown worth of the GCRE-1 mock-up safety and control blades were obtained. The critical assembly consists of aluminum tubes containing four concentric stainless steel cylinders wrapped wtth highly enriched uranium foil. These tubes are supported at each end by grid plates aiid arranged t… more
Date: September 10, 1958
Creator: Dingee, David A.; Ballowe, William C.; Klingensmith, Raymond W.; Egen, Richard A.; Jankowski, Francis J. & Chastain, Joel W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experiments to Determine the Radiation Stability of UN Dispersions in Stainless Steel

Description: A controlled radiation experiment was performed to determine the stability of fuel containing 28 wt.% UN dispersed in and clad with Type 318 stainless steel as compared with fuel containing 30 wt.% UO/sub 2/ dispersed in the same material. The specimens were prepared by hot rolling the fuel coupons in Type 318 stainless steel using the picture-frame technique for initial bonding and reduction. Final dimensions were obtained by cold rolling. A special radiation capsule was designed which contain… more
Date: June 14, 1960
Creator: Gates, John E.; Freas, David G.; Saling, James H. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation and characterization of tritium targets. [Titanium tritide]

Description: The Isotope Research Materials Laboratory (IRML) of the Oak Ridge National Laboratory (ORNL) prepares tritium targets that are used to produce an intense beam of 14.5 MeV neutrons by the /sup 3/H(/sup 2/H,/sup 1/n)/sup 4/He reaction. The intense beams of 14.5 MeV neutrons are used in programs involving cancer research, materials evaluation, and materials identification. The tritium targets required by researchers have ranged in size from 1-cm diam to 50-cm diam and have contained from 3.7 x 10/… more
Date: January 1, 1982
Creator: Ramey, D. W. & Adair, H. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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LWR-PV damage estimate methodology

Description: A credible estimate of the pressure vessel lifetime due to neutron-induced embrittlement is studied. The first step toward this goal is the accurate prediction of fluence and neutron energy spectrum at the pressure vessel. This, in turn, is obtained from least squares unfolding techniques of dosimetry measurements at a surveillance position, transport calculations, and a translation of information obtained at the surveillance position to the damage position. Including a prototypic neutron field… more
Date: January 1, 1980
Creator: Wagschal, J.J.; Maerker, R.E. & Broadhead, B.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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