Final report on Production Test 105-528-A -- Alteration of two C-Pile horizontal safety rods for temperature distribution control (open access)

Final report on Production Test 105-528-A -- Alteration of two C-Pile horizontal safety rods for temperature distribution control

Pile temperature control is normally maintained by using four horizontal rods, two ``long`` rods extending to the far side of the pile and two ``short`` rods whose tips are on the near side. (1) This procedure prevents cycling of ``hot spots`` about the pile, but does not achieve symmetrical horizontal temperature distribution. Prior to pile operation the cadmium-containing cans were removed from the near ends of the two ``long`` control rods, numbers 5 and 11, at C pile, so that when these rods were in the ``full in`` position their poisoning effect outside the flattened region at the near side of the pile would be small. By using these ``half rods`` in conjunction with ``short`` rods it was expected that a nearly symmetrical horizontal temperature distribution could be maintained. A comparison of near-to- far temperature distribution at C-pile with other piles indicates that gains in production of 4% during early operation of a pile and 3% during later equilibrium operation can be realized by using the half-rods. On the basis of these observations ``half-rods`` are to be incorporated in the K-piles currently under construction. It is recommended that the ``long`` control rods in existing piles be replaced by rods altered …
Date: June 11, 1953
Creator: Halliday, A. W.
System: The UNT Digital Library
Conversion efficiency and U{sup 235} depletion in H-10 (open access)

Conversion efficiency and U{sup 235} depletion in H-10

Preliminary observations on tritium production fro extracted Z slugs in the H-10 load indicated yields which were lower than those calculated by approximately twenty percent. The calculated conversion efficiency for loading is 0.835. Results of a measurement of the conversion efficiency for three separate tubes are reported and found to be lower than 0.835 by approximately twenty percent, or very nearly the same as the discrepancy in tritium production. The values measured are 0.67, 0.61, and 0.60 for the three tubes respectively. Details of 25 burnup calculations are also presented with a measured depletion factor of 0.584 grams of 25 destroyed. Reasons for the large discrepancy in conversion efficiency are not known at the present time. However, some possibilities are discussed.
Date: August 11, 1953
Creator: Peterson, R. E.
System: The UNT Digital Library
PROBABILITY DISTRIBUTIONS OF TWO SINUSOIDS IN NOISE (open access)

PROBABILITY DISTRIBUTIONS OF TWO SINUSOIDS IN NOISE

None
Date: August 11, 1953
Creator: Gragg, D.M. & Tiede, K.F.
System: The UNT Digital Library
CORE SHAPE OF FUEL ELEMENTS CLAD WITH ZIRCONIUM ALLOY (open access)

CORE SHAPE OF FUEL ELEMENTS CLAD WITH ZIRCONIUM ALLOY

None
Date: June 11, 1953
Creator: Holladay, J.W.; Kura, J.G. & Jackson, J.H.
System: The UNT Digital Library
ENGINEERING PROPERTIES OF DIPHENYL (open access)

ENGINEERING PROPERTIES OF DIPHENYL

None
Date: August 11, 1953
Creator: Anderson, K.
System: The UNT Digital Library
Application of the mercury-catalyzed aluminum jacket dissolving technique to the Redox process (open access)

Application of the mercury-catalyzed aluminum jacket dissolving technique to the Redox process

The possible means of removing aluminum jackets from uranium slugs were considered before Hanford start-up in 1944, and have been considered at other sites for processing other types of slugs. The sodium hydroxide-sodium nitrate dissolution, which served well for Bismuth Phosphate plant operation was accepted for use in the Redox plant. The other means of jacket removal, namely, dissolving the jacket in nitric acid with the aid of mercury as a catalyst, has been adapted for use at Arco and offers certain possible advantages for Redox Plant operation. The primary purpose of this document is three-fold: To report exploratory experimental work performed to date in the Process Chemistry laboratories on the study of the dissolving reaction and the properties of the resultant feed solution; to present a summary of the status of related work at other sites and by other groups at the site, as determined from a survey of the available literature references; to outline questions yet to be answered before the process may be used in the Redox Plant and a program to be followed to answer these questions.
Date: December 11, 1953
Creator: Curtis, M. H.; Bradford, J. L. & Harmon, M. K.
System: The UNT Digital Library
Trip report, BMI, August 7, 1953 (open access)

Trip report, BMI, August 7, 1953

None
Date: August 11, 1953
Creator: Beckman, G. W.
System: The UNT Digital Library
Summary and correlation of water quality testing results (open access)

Summary and correlation of water quality testing results

A considerable technical effort has been expended during the past two years in evaluating the effects of various process water qualities on the corrosion of aluminum tubes and slugs. Primary emphasis has been placed on four types of water: ferric sulfate coagulated water with and without dichromate addition, and alum coagulated water with and without dichromate addition. Both in-pile and flow laboratory data have been obtained on the corrosivity of these several water qualities. It appears that a review of the available information will serve two useful purposes. First, a comparison of corrosion data from all available sources will provide a better overall understanding of the corrosive properties of the various types of water. Second, a knowledge of the applicability of small scale and mock-up tests to actual in-pile operating conditions will permit more efficient experimentation in current work aimed at raising outlet water temperatures, reducing water treatment costs, and reducing corrosion rates of pile components. The purpose of this report is to present a summary and correlation of flow laboratory and in-pile corrosion data in various qualities of process water.
Date: November 11, 1953
Creator: Miller, N. R.
System: The UNT Digital Library
Uranium-Zirconium Explosions in Nitric Acid (open access)

Uranium-Zirconium Explosions in Nitric Acid

None
Date: May 11, 1953
Creator: Russell, R.B.
System: The UNT Digital Library