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THE EXAMINATION AND EVALUATION OF IRRADIATED THORIUM-11 w/o URANIUM SPECIMENS

Description: Twelve irradiated specimens of thorium -11 wt.% U were examined. The specimens were fabricated by induction melting and casting in graphite and cold swaging to about 42% reduction in area. The irradiations were conducted in the MTR in capsules equipped with thermocouples. Six specimcns were irradiated to burnups ranging from 0.5 to 0.6 total at.% at average central corc temperatures ranging from 1070 to 1250 F. Three spccimens exbibited sevcre swelling or decrepitation and three appeared to be … more
Date: April 16, 1959
Creator: Gates, J.E.; Lamale, G.E. & Dickerson, R.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Local control strength change due to overboring

Description: The possibility of overboring in existing Hanford reactors to increase slug size has been suggested as a means of increasing production. The effect on control system strength of such a modification is, of course, one of the factors which must be considered. This report presents the results of a study requested by the Reactor Physics Unit of the local buckling of control rods as a function of the migration area. The migration area varies for different lattice make-ups, but due to the complexity,… more
Date: December 16, 1959
Creator: Bowers, C. E. & Montague, D. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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METALLURGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1959

Description: 7 = 9 9 9 9 7 7 7 = 9 9 9 95 : > @ 9 ; 5 8 @ = K : . ighpurity Nb deformed by impact or slow compression at - 196 deg C. An apparent phase transformation was detected in high- purity Ga deformed at 4.2 deg K. The specific heat of the group IV-A metals and alloys of Zr-In and Zr-Sn were measured from 1.2 to 4.5 deg K. In the Zr-rich portion of the Zr-Ga phase diagram, the alpha / beta phase boundaries of Zr are depressed by additions of Ga and the beta phase decomposes by a eutectoid reaction. T… more
Date: December 16, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NUMERICAL SOLUTION OF TRANSIENT AND STEADY-STATE NEUTRON TRANSPORT PROBLEMS

Description: A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transport equation is described. The main topics relate to the derivation of suitable difference equations, and to the problem of solving these, while maintaining generality, accuracy, and reasonable computing speed. A few comparisons with other methods are made. (auth)
Date: May 16, 1959
Creator: Carlson, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pressure bonding Zircaloy-2 clad fuel elements

Description: A metallurgical bond can be effected between a Zircaloy-2 jacket and a thin walled uranium tube by treatment in a high temperature, high pressure gas autoclave. Bonding is independent of core history, provided that all surfaces are free from contamination. Gas pressure bonding causes the fuel element jacket to conform to the core, which promotes bonding on all surfaces including the ends. Grain growth occurred in some instances between the jacket and end cap interface. A three phase system (alp… more
Date: November 16, 1959
Creator: Tverberg, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-2-A: Enriched uranium conversion and stability test, Final report

Description: The purpose of this test was (1) to determine the conversion ratio of alternated enriched uranium fuel segments and lithium aluminum target slugs, and (2) to determine the stability of solid and cored enriched uranium with this type of load. The test consisted of an irradiation of two twelve-tube pile charges, each of them forming a sixteen tube square without corners. The first twelve tubes were a ``striped`` load containing solid fuel elements enriched to .95% U-235 alternated with lithium-al… more
Date: January 16, 1959
Creator: Lang, L. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-288-A, evaluation of seven-rod cluster elements with modified end closures

Description: Objective of this production test is to obtain irradiation experience wit the hot-headed closure for co-extruded Zircaloy-2 jacketed rod. Seven Zircaloy-2 jacketed natural uranium seven-rod cluster elements with hot-headed end closures and spark machined end supports will be irradiated in the KER Loops to an exposure of 2000 MWD/T in pH 8--11 coolant.
Date: October 16, 1959
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposed Helium Purification System for the Experimental Gas-Cooled Reactor (EGCR)

Description: Liquid and dry processes suituble for the purification of gases by the removal of CO/sub 2/, H/sub 2/O, CO, H/sub 2/, and hydrocarbons are discussed. Recommendations are given for specific processes io be included in a "dry" (no liquid absorbents or chemicals used) purification system for the hellum coolant of the EGCR The recommended processes include (1) a catalytic converter for the oxidation of CO, H/sub 2/, and hydrocarbons to CO/sub 2/ and H/sub 2/O, (2) cooler-condensors for the removal … more
Date: October 16, 1959
Creator: Anderson, F.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PT-IP-158-D, Supplement B: Irradiation of one swaged UO{sub 2} stainless steel clad fuel element in a KE front-to-rear test hole

Description: The objective of this supplement is to authorize a change in the panellit trip range from 25--75 psi to 5--95 psi. The test hole facility consists of two concentric aluminum tubes which extend from the front face to the rear face of the reactor. The ID of the inner tube is 2--7/8 inch. Water from one crossheader supplies the annulus, water from another crossheader supplies the inner tube. The three-foot-long, .570 inch OD fuel element is centered in a 40-inch long aluminum holder which has an I… more
Date: February 16, 1959
Creator: Marshall, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The radioisotope osteogram: Kinetic studies of skeletal disorders in humans

Description: Radioactive strontium can serve as a tracer to gain information concerning calcium metabolism in human subjects. Gamma-emitting Sr{sup 85} is used rather than the much more hazardous, beta-emitting Sr{sup 89} and Sr{sup 90}. (ca{sup 47} -- the ideal tracer for normal calcium -- is quite expensive and difficult to procure.) Very significant information may be obtained merely by measuring and recording the changes in radioactivity in various body areas during the first hour after intravenous inje… more
Date: October 16, 1959
Creator: MacDonald, N.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiometallurgical examination of PT-IP-221-A measurement of flow channel temperature in 7 rod cluster fuel element (RM-287)

Description: Eight Zircaloy-2 jacketed, natural uranium seven-rod cluster elements were irradiated in a KER loop to determine flow channel temperature characteristics. One of the elements, which had 200 MWD/T exposure, was sent to the Radiometallurgy Laboratory for examination in April 1959. An outside rod of the cluster was sectioned and examined metallographically. No cracks or flaws were observed in the uranium cladding or bonding.
Date: June 16, 1959
Creator: Teats, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ROLLING AND WELDING TYPE 430M TUBES TO STAINLESS STEEL OVERLAID CARBON STEEL TUBE-SHEETS. SM-1 (APPR-1) RESEARCH AND DEVELOPMENT PROGRAM. Task No. X.

Description: In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tubesheets to ASTM Specification A350-Grade LF-1, modifled with 1.66% nickel; and weld the tube ends to the stainless steel overlay previously applied to the tubesheet. The rolled joint was a necessary precaution to prevent secondary water, that might contain chlorides, from contacting the stainless steel weld joining the tubes to the tubesheets. The welded joint provid… more
Date: February 16, 1959
Creator: Bennett, R.W.; Meister, R.P. & Kerton, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Supplement C -- Production test IP-64-CE poison column displacement during reactor operation

Description: The objectives of this supplement are to test an improved prototypic slug column displacement winch and associated remote control equipment and to demonstrate the feasibility of exerting control over the front-to-rear neutron flux changes as an aid in controlling reactivity cycling. An array of poison displacement columns up to twelve in number is intended, each charge consisting of a center section of I and E natural uranium slugs with mint pieces on each end. Initially six such columns will b… more
Date: June 16, 1959
Creator: Hedges, J. W. & Carter, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TEMPERATURE STRUCTURE IN THE GAS COOLED REACTOR FUEL ELEMENTS USING A SCALLOPED COOLANT CHANNEL

Description: An analysis of the temperature structure in the GCR2 fuel elements and coolant stream at the position where the maximum fuel element surface temperature exists was presented in a previous paper (CF-58-5-97). It was felt that the peripheral temperature variation existing on the fuel rods as brought out in that analysis was due mainly to the poor flow distribution of the coolant with respect to the heat flux. The most expedient way to alleviate this situation without changing the fuel element ass… more
Date: March 16, 1959
Creator: Epel, L.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Cycling of Plutonium. Part I. Observations of the Physical Damage Resulting From Thermal Cycling Plutonium Through Its Low Temperature Phase Transformations

Description: Plutonium, thermally cycled through the low-temperature allotropic transformations, exhibited extensive physical damage. The physical damage was greater than that reported for any other metal or alloy. The extent of physical damage was determined by measurements of fluid displacement and the dimensional changes. The internal porosity was examined metallographically. Physical damage varied considerably, depending on the cycling conditions and the characteristics of the metal (particularly inclus… more
Date: September 16, 1959
Creator: Nelson, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE USE OF INCONEL AS A HIGH TEMPERATURE, CORROSION RESISTANT, THERMAL NEUTRON FLUX MONITOR

Description: Inconel can be used for thermal neutron flux measurements by means of its cobalt impurity or its chromium constituent where conventional monitors are unsuitable. The use of cobalt should also be applicable to other nickel alloys. Discriminatory counting is required. (auth)
Date: March 16, 1959
Creator: Guss, D.E. & Leddicotte, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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