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ORGDP Container Test and Development Program Fire Tests of UF6-Filled Cylinders

Description: Fire tests of bare, UF{sub 6}-filled shipping cylinders were conducted at the ORGDP Rifle Range during October 1965 as part of the AEC-ORO Container Test and Development Program presently under way at the ORGDP. The multi purpose effort was to determine if the cylinders would hydrostatically or explosively rupture; the time available for fire fighting before either incident occurred; and the degree of contamination as related to the type of UF{sub 6} release, wind velocity, and terrain. In addition to the cylinder fire tests, other tests were made for further evaluation of the fire-resistant BOX foam plastic. These included a newly designed shipping drum for 5-in.-diam cylinders, and 15B-type wood shipping boxes for small containers. In one case, the latter contained a UF{sub 6}-filled Harshaw cylinder. The test times ranged from 45 to 95 min. In no instance did temperatures exceed 200 F These tests are discussed under Part B. Our Nuclear Engineering Department was responsible for site preparation and the test program. The Safety and Health Physics Departments Mr. A. F. Becher, head, provided primary assistance in the conductance of the tests and was additionally responsible for the environmental monitoring and sampling. Personnel of the Plant Shift Operations and Security, Fabrication and Maintenance, and Technical Divisions provided further support in the various operations. Mr. J. E. Wescott of the AEC-ORO and Mr. J. W. Edwards, ORGDP, were in charge of the motion and still photography. Two each of the following types of cylinders were tested: 3.5 in. diam x 7.5 in. Monel Harshaw, 5.0 in, diam x 30 in. Monel, and 8 in. diam x 48 in. nickel. Fill limits were 5, 55, and 250 lb of UF{sub 6} respectively, at an enrichment level of 0.22%. The larger cylinders were tested individually, with and without their metal valve covers. ...
Date: January 12, 1966
Creator: A.J., Mallett

Filling and Emptying System, Cannelton Main Lock, Ohio River, and Generalized Tests of Sidewall Port Systems for 110- by 1200-ft Locks: Hydraulic Model Investigation

Description: Report providing the results of a hydraulic model investigation of the Cannelton Lock proposed for construction on the Ohio River. It includes detailed information about the tests and suggested dimensions and features of the final lock.
Date: February 1966
Creator: Ables, Jackson H., Jr. & Boyd, M. B.

Filling and Emptying Systems, Low-Lift Locks, Arkansas River Project: Hydraulic Model Investigation

Description: Results of a hydraulic model investigation based on locks in the Arkansas River before the construction of additional locks. "Model studies of the filling and emptying system proposed for use at the low-lift locks in the Arkansas project were conducted to confirm the adequacy of the original design hydraulic system, and to develop, if needed, improvements in the system" (p. 2).
Date: November 1966
Creator: Ables, Jackson H., Jr. & Boyd, M. B.

The Columbia River Cooling Program CY-1965

Description: The Columbia River Cooling Program basically consists of effecting a reduction in river temperature at the Hanford site during the summer season. The implementation of this program in recent years has been accomplished through the selective and controlled discharge of waste water at Grand Coulee Dam. The purpose of this report is to describe the river cooling program conducted in CY-1965 by Facilities Engineering personnel, and present the program results.
Date: April 15, 1966
Creator: Adachi, W. N. & Ballowe, J. W.

Reactor Development Program Progress Report: September 1966

Description: Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.

Operation of a Reverse Osmosis Desalination Pilot Plant

Description: Report demonstrating the technical feasibility of desalination by the Reverse Osmosis Process in a pilot plant cell containing 100 square feet of membrane area. A group of experimental tests are performed relating the desalination cell performance to the operating variables of brine flow rate, pressure, and brine concentration.
Date: 1966
Creator: Aerojet-General Corporation

K Reactor uncooled HCR: Equilibrium temperature study

Description: Temperature calculations were made on a proposed design of an uncooled horizonal control rod (HCR) for the K Reactors. The calculations were performed with the aid of a FORTRAN coded heat transfer program for the UNIVAC 1107. The results of the calculations indicate that such a control rod is feasible for.4400 Mw and 5000 Mw operation provided certain precautions are taken. These precautions include assuring good contact between the rod and the graphite in the high flux regions and Providing reasonable contact between the graphite stack and the graphite slider plates that will be placed in the bottom of the rod channels prior to rod insertion and use.
Date: January 24, 1966
Creator: Agar, J. D.

NUCLEAR SPECTROSCOPIC STUDIES OF SOME VERY HEAVY ODD-MASS NUCLIDES

Description: The nuclear radiations of nuclides: U{sup 233}, Pu{sup 239}, Bk{sup 243}, Bk{sup 244}, Bk{sup 245}, Bk{sup 246}, Bk{sup 249}, Cf{sup 249}, and Fm{sup 255} were investigated with high-resolution spectrometers. The {alpha}-particle spectra of all nuclides except Bk{sup 249} were measured with 6 mm diameter surface-barrier detectors. Bk{sup 249} {alpha}-particles were analyzed with a double-focusing magnetic spectrograph. The {gamma}-singles were examined with the recently developed Ge(Li) and Si(Li) detectors coupled with very-low noise 'internal FET' preamplifiers. Weak alpha groups were observed in coincidence with {gamma}-rays, detected with a NaI(Tl) scintillation spectrometer. To improve the over-all coincidence efficiency a new coincidence apparatus was designed and built. This instrument consisted of a cooled 4.5 cm diameter semiconductor detector for {alpha}-particle detection and a 3 cm diameter by 2.7 cm long Ge(Li) detector for {gamma}-ray analysis. The Ge(Li) detector could also be replaced with a NaI(Tl) detector. Cf{sup 249} conversion electrons were measured with a cooled Si(Li) detector coupled with an internal FET preamplifier. On the basis of the present work and previous information, energy-level diagrams of the daughter nuclei have been constructed. The levels have been grouped into rotational bands built on Nilsson single-particle states. Because of identification of several rotational members of the bands, definite Nilsson quantum number assignments have been made in most cases. The alpha intensity calculations of Poggenburg were found quite helpful in making these assignments. A strong Coriolis effect was observed in the Am{sup 245} levels populated by the alpha groups of Bk{sup 249}. Calculations were made with Nilsson wave-functions, and these were found to agree with the experimental results. The Coriolis interaction was found important in almost all cases; the effect was very noticeable in the level spacings between the rotational members of the bands. High-lying bands in Cm{sup 245} (at 644 keV) and cf{sup 251} (at ...
Date: September 20, 1966
Creator: Ahmad, Irshad

Abstract -- A description of low temperature hydriding of zircaloy at Hanford

Description: The two K Reactors at the Hanford Plant of the Atomic Energy Commission were retubed in 1963 with ribless Zircaloy process tubes. These tubes, 1.81 inch OD x 0.037 inch wall, were made by tube reducing methods from extruded blooms and were installed without final pickling or autoclaving. These tubes are used with once-through filtered water with a maximum coolant temperature of approximately 110 C. After approximately two years` service, it was discovered that these tubes were absorbing hydrogen in a totally unexpected and alarming manner. It was found that the downstream few feet of these tubes had a layer of massive hydride platelets, several mils thick, on the inner surface, and that the hydrogen content of the tube wall beneath this layer had increased from the as-fabricated level of 5--15 ppm to 50--75 ppm. The portion of the tubes so affected was downstream of the fuel charge. Physical testing has indicated loss of ductility but no significant changes in strength, Cold burst tests resulted in a ductile failure mode with no tendency toward brittle fracture. A program to determine the basic mechanism responsible for this phenomenon as well as practical means for its elimination will be the subject of a companion paper.
Date: March 31, 1966
Creator: Alexander, W. K.

Experimental design for the preliminary study of geochemical processes

Description: An example of the use of a simple fuctorial design to study the distribution of /sup 134/Cs and/sup 85/Sr between a soil column and solution is reported. In this design, two concentration levels of each of four factors (NaNO/ sub 3/, HNO/sub 3/, KNO/sub 3/, and Ca(NO/sub 3//sub 2/) were combined in all possible combiuations to give a total of 24 combinations. In the case of /sup 134/Cs removal, all of the independent variables were significant over their respective concentration ranges, while with the removal of /sup 85/Sr, none of the independent variables was statistically significant. Extending the concentration range of NaNO/sub 3/ caused the NaNO/sub 3/ effect total to become statistically significant at the 5% t-test level in its effects on /sup 85/Sr removal. A fractioral factorial design was used to study the removal of Sr from solutions into an apatite during a chemical reaction between phosphate ion and calcite. The Yates analysis of the Sr removal data is tabulated. It is noted that even at a t-test level of 1%, calcite surface area, influent solution pH. and system temperaturesolution pH interaction are statistically significant. The two-level factorial design yields no direct indication of the Sr removal mechanism but does suggest that a chemical reaction is involved. (JGB)
Date: March 24, 1966
Creator: Ames, L.L. Jr. & Hajek, B.F.