None

None

None

None

None

None

None

Preliminary designs and costs have been developed for nuclear fuel head-end reprocessing facilities integral with a large High-Temperature Gas-Cooled Reactor (HTGR) power plant.

None

None

None

The results of our assessment of the processing methods and costs for the recovery of cesium, techneium, rhodium, and palladium from aged waste supernates are presented. Guidelines for the assessment of costs are given. Cesium can be readily absorbed from alkaline waste supernates without prior treatment using Linde AW-500, a synthetic zolite. Technetium, present in the supernate as the pertechnetate anion, together with rhodium and palladium, probably present as anionic nitrite complexes, can be absorbed from untreated waste supernates using Dowex 1-X4 or similar anion resins. Although the behavior of cesium and technetium is reasonably well understood, the behavior of the anionic complex that accounts for the presence of rhodium and palladium in this strongly alkaline solution is not well understood. Further work is required before a process can be outlined for the clean separation of rhodium and palladium from the technetium-rhodium-palladium crude fraction sorbed on the anion resin. An assessment of capital and operating costs for the recovery of cesium only, technetium only, or both cesium and technetium are tabulated. No costs are shown for rhodium and palladium, since the technology for their separation is not sufficiently advanced. However, the incremental cost for their separation from technetium is expected …

None

None

An aerothermodynamic analysis of the SNAP-27 LEM fuel cask is presented for each of three mission aborts. Aerodynamic models for point mass and six degree-of-freedom trajectories are used, and the fuel cask heating rates and temperature responses are predicted for these trajectories. A survey of analytical and experimental studies of separated flow is related to the fuel cask, and a shock tunnel test program is outlined for further fuel cask analyses.

Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks and modifications to the original cask design to insure its safe use. The design criteria was developed in January 1963 by an ad hoc committee comprised of representatives of the Chemical Processing Department, Hanford Laboratories, and Construction Engineering and Utilities of General Electric Company. The various tests, calculations and modifications of the cask were conducted by the Chemistry Department of Pacific Northwest Laboratory.

The transverse electromagnetic coupling of bunches of particles with each other is investigated theoretically, and shown to incorporate the possibility (due to the effect of nonperfectly conducting vacuum chamber walls) of coherent instability even when the longitudinal distance between bunches is much larger than the transverse dimensions of the vacuum tank. The modes of oscillation in which the bunches move rigidly are investigated; criteria for stability, and expressions for the small amplitude growth rates under unstable conditions are presented. The case of a single bunch is considered in detail and demonstrated to be stable (even in the absence of landau damping) provided {nu} lies between an integer and the next higher half-integer, where {nu} is the number of transverse free betatron oscillations occurring in one revolution; for many bunches which are sensibly different in intensity (a criterion for this is presented), all modes are stable provided {nu} satisfies the same restriction. For equally spaced bunches of equal numbers of particles, approximately half the modes are unstable without Landau damping. Numerical examples are presented covering some intermediate situations.

None

A soil map and a descriptive report of Hanford Area soils grouped according to morphologic and genetic characteristics are presented.

A method for determining numerically local minima of differentiable functions of several variables is described. In the process of locating each minimum, a matrix which characterizes the behavior of the function about the minimum is determined. For a region in which the function depends quadratically on the variables, no more than N iterations are required, where N is the number of variables. By suitable choice of starting values and without modification of the procedure, linear constraints can be imposed upon the variables. 8 figures.

Thermal diffusivity of Al-clad MTR-ETR type fuel plates was measured from room temperature to 600/sup 0/C. (DLC)

Plant nutrition was studied as a relation between aerobic respiration and ion uptake in barley. Potassium, chlorine, lithium, sodium, calcium, sulfates, and bicarbonates were studied by root absorption in varying concentrations of carbon dioxide atmospheres. (PSB)

Basic surface-water and precipitation data collected from June 1961 through June 1965 at 10 stations in Lower Little Creek basin of Lamar and Marion Counties, Mississippi, are presented. The U.S. Atomic Energy Commission's Tatum dome site of Project Dribble is in Lower Little Creek basin. The data show a 3.80-inch deficiency in precipiation in the Tatum dome are from April 1964 through June 1965 and an 11.72-inch deficiency from June 1961 through June 1965. The mean monthly discharge at Lower Little Creek (4892.40) was less than the median monthly value during 11 of the 15 months from April 1964 through June 1965. Chemical analyses of water samples collected from five streams in the Tatum Dome area indicate that the water is of generally good quality; for example, dissolved-solids content ranged from 16 to 23 parts per million for samples collected during the period from October 31, 1961, through October 23, 1964. 4 figures, 4 tables.

A thermal analysis was carried out to determine the temperature distribution in a SNAP-8 type reactor system during atmopsheric reentry. Of particular interest are the temperature distributions in the reactor upper head, the upper grid plate, and the vessel wall. The time and altitude were determined at which the upper head falls away from the reactor core due to having a portion of its wall melted through. The time and altitude of the melting of the upper grid plate and vessel wall were also determined. The effects of reentry attitude or equivalent angle of attack and initial temperature on the thermal behavior of the system were investigated. The computer programs used in various phases of the analysis were NEWTON (drag coefficient), RESTORE (reentry trajectory), and TAP (thermal model).