The development of apparatus and laboratory techniques for the study of materials compatibility with 1500 to 2200 deg F potassium was attempted. Techniques for corrosion tab preparation, dry box capsule filling and sampling, and vacuum filling and sampling are described. Apparatus for rotating capsule testing to 2000 F, rotating capsule testing to 2400 deg F, and anisothermal see-saw'' capsule testing is also described. (auth)

The effect of the many parameters which may influence the failure behavior of coextruded fuel material are being evaluated by Reactor & Fuels Research & Development Operation. This knowledge will be helpful in the design, fabrication, and operation of fuel elements so that the hazards and time involved at failure may be minimized. Many of the various tests performed on unirradiated coextruded fuel material have been in isothermal systems. The tests reported here were performed on power generating coextruded fuel rods. One of the purposes of these tests was to assess the effect of simulated in-reactor power generation and associated thermal gradients and thermal stresses on the defect-test behavior. Another purpose of these tests was to determine the degree of damage that might result to fuel components as a result of interaction (e.g., touching produced by warping or distortion of a failing rod) while at operating powers.

Results of studies of the known parameters for direct calcination of plutonium nitrate in an agitated bed and conversion of PuO/sub 2/ to PuCl/sub 3/ by fluid bed processes are presented. A description of the processes and the demonstration equipment is included. The study of variables is discussed along with the parameters and plans for demonstration runs. (J.R.D.)

The gamma heat generations in selected positions of the ETR were measured for Cycles 27, 33, and 34. The measurements for Cycle 27 include data for the clean core and depleted core. Maximum gamma heat generation maps are presented for each cycle along with vertical traverses for all positions monitored. The measurements were made using a graphite- C0/sub 2/ ionization chamber. (auth)

Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuunn arcs; ion production; acceleration and injection; plasma theory and computations; instrumentation; magnetics; cross-section measurements; vacuum systems and techniques; bell- lightning; and design and engineering. Separate abstracts were prepared for the 11 sections. (B.O.G.)

Experimental results are summarized for investigations on the condenser fluid mechanics of mercury under zerogravity, two-phase conditions. Conditions required for interfacial stability in tubes were determined as a function of tube diameters. Correlated two-phase pressure drop data are presented as functions of tube inlet Reynolds number and vapor specific volume. Flow regime stability was studied under zero-gravity and 2.55-gravity conditions and at various Reynolds numbers. the effect of noncondensable gas on flow performance in mercury forced convection condensers was evaluated. (D.L.C.)

The Reactor Nuclear Data Tape Programs were designed to compile and/or modify a nuclear data library tape from basic nuclear cross-section input. It is intended that this cross-section library tape will be utilized to provide up-to- date nuclear data for various reactor codes. Program RNDP was designed to compile an initial tape from certain minimal input data, or to add or delete complete blocks of data from an existing tape. Program RNDM was designed to compile and add to an existing tape macroscopic cross section data consisting of mixtures of microscopic cross sections available on the tape. Program RNOC was designed to modify and copy an existing tape, or to compile a new tape from sets of binary cards punched by Program RNDP. These programs were written using the FORTrAN-II system of automatic coding for the IBM7090. (auth)

The distortion behavior of graphite as a function of irradiation temperature is reviewed. The behavior of needlecoke and CSF graphite was examined over moderate exposures in the GETR. Results showed needle-coke to be less contracting than CSF. Details of contraction show a minimum contraction rate per 10/sup 21/ nvt at 600 to 800 deg C for both types. Limitations to be placed on the data presented are listed. (P. C.H.)