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A device is described for the filtration of charged energetic heavy particles resulting in the production of adjacent or separated Bragg peaks within the range of the particles in tissue. Two or more layers of intense ionization at different depths separated by layers of less ionlzation in tissue can be produced. A cylinder of uniform ionization which cuts off sharply in depth in tissue can also be produced. (auth)

For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)

The TUT-T5 code for the IBM-704 estimates neutron capture probabilities in a one-energy, two-dimensional, rectangular cell model, using a Monte Carlo method. The problem and its solution are described in mathematical terms. The transport equation arising from the idealized physical model used in the code is derived and the problem is stated in terms of the solution of this equation. The validity of the Monte Carlo solution is established by proving that the random variables involved are unbiased for processes with convergent Neumann series. These random variables sum the distances travelled by randomly selected particle histories and use these sums to estimate flux integrals over the various regions. Capture probabilities are then obtained through multiplication by the appropriate capture cross sectione. The integrals which express the variances of these random variables appear too complicated to handle by analytic methods. (auth)

At the end of 1959, 25% of the construction and 85% of the firm design of the Heavy Water Components Test Reactor (HWCTR) were complete. Further safeguards analyses of the HWCTR, done with the aid of analog and digital computers, corroberated earlier data which indicated that the reactor is highly self-regulating, and that the safety system should prevent release of radioactivity outside the containment building. Fabrication tests of metallic uranium fuels and preparation of irradiation specimens of swaged uranium oxide fuel tubes continued. A tube of Zircaloy-2-clad U-2 wt.% Zr failed during a low temperature, low pressure irradiation test to modest exposure. Preliminary examinations of tubular metallurgical joints between Zircaloy and stalnless steel were promising. (For preceding period see DP-445.) (J.R.D.)

The testing of Zircaloy at various stages of processing by ultrasonic techniques is described A study was made to determine the feasibility of substituting ammonium bifluorlde for the liquid hydrofluoric acid generally used in the etching processes required for the fabrication of Zircaloy fuel coniponents The addition of B to Zr results in a very strong alloy however. they show little proniise for being ductile. Zirconium-boron alloys can be hot forged Boron is very detrimental to the oxidation behavior of Zircaloy-2. (W.L.H.)

This report is the first quarterly report under Contract AT(30-1)-2528 for the decontamination and recovery of precious metals from contaminated scrap. This program encompasses the recovery of gold, platinum, iridium, rhodium and palladium from scrap and contaminated laboratory ware, equipment, etc. which may be contaminated by alpha emitters (i.e., uranium, plutonium and possibly polonium or combinations of these), beta-gamma emitters such as fission products or all three sources of radiation. In addition the scrap can be chemically contaminated by base metals, graphite or other contaminants. Osmium, ruthenium or silver are not to be recovered. Since the scrap can exist in such a great variety of forms such as platinum-rhodium laboratory crucibles, graphite crucibles containing platinum-base metal alloys derived from vacuum fusion baths, insulated thermocouple wires, reactor liners, porous platinum filters, alloys such as Baker alloy 413 (60 Au, 25 Pd, 15 Pt) it may be necessary to devise specific methods for a given type of scrap. Nevertheless the basic chemistry is the same and information and methods applicable to single systems will apply directly to the more complicated ones. Accordingly the relatively simple systems would be investigated first and the more complicated ones later in the program. An essential and …

The steady-state temperature structure for a cross sectional area at the midplane of the EGCR fuel rod is presented. The temperatures are given for the UO/sub 2/ as well as for the stainless steel tubing and spacer. (auth)

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A review is presented in this symposium of the technology currently available for processing spent fuels from research, test, and power reactors. Twenty-one papers are included. Separate abstracts have been prepared for each paper. (W.L.H.)

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A study has been made of the wear and friction phenomena associated with sliding molybdenum surfaces lubricated by liquid sodium. Operating conditions included sodium temperatures from 250 to 1300 deg F, sliding speeds of from 0.22 to 2.5 nan per sec, and contact stresses of 80,000 psi. Sliding specimens consisted of a ball and a flat rectangle. Sodium was found to influence the sliding behavior of molybdenum by modifying reacted films which provided boundary lubrication. These effects were also found to be temperature dependent. Addition of clean sodium between dry rubbing molybdenum surfaces in an argon atmosphere of high purity produced a marked drop in friction coefficient, and the character of the wear scar changed from galling to superficial scratching. Furthermore, these effects persisted after removal of sodium by evaperation. Studies of the films formed on molybdenum surfaces during sliding in liquid sodium and under controlled atmospheres were carried out using electron and x-ray diffraction, electron microscope, and differential thermal-analysis techniques. It was established that a sodium molybdate film on the molybdenum surfaces can be associated with low friction and diminished surface damage. Studies in vacuums up to 10/sup -6/ mm of mercury showed that native oxides on molybdenum also …

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This document resents the development program for the SNAP 4 Compact Power System. The development plan leads to the development of two power plant concepts that use an identical reactor but differ only in the power conversion systems.

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