This report addresses the summary report of the Chemical Engineering Division.

None

Fabrication techniques for producing dispersion fuel elements with cores of 30 volume per cent of UC, U/sub 2/Ti, U/sub 3/Si, or U/sub 6/Ni dispersed in Zircaloy 2 and 30 volume per cent of UC or UN dispersed in Type 18-8 stainless steel have been investigated. Roll-clad plate-type elements of all these compositions may be fabricated by powdermetallurgy methods in such a manner that good core-tocladding bonds and cores with uniform dispersions of discrete uranium- compound particles are obtained. From the standpoint of fabricability, elements containing UC in Zircaloy 2, UC in stainless steel, and UN in stainless steel are the most promising. The UN in stainless steel has the best corrosion resistance in 680 deg F degassed water; however, UC in stainless steel has the best resistance to corrosion in 700 deg F NaK. (auth)

The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed. (auth)

None

None

None

The rates of growth of diffusion layers between U and Al and between U and AlSi alloy (eutectic composition) were studied and compared over the temperature range 250 to 55O deg C. Metallographic observation shows that the U-- Al reaction layers form three to five times as fast as the U-- AlSi layers over this temperature range. Sixty per cent of the layer growth takes place in the Al or AlSi alloy and 40% in U. (auth)

None

This is a revision of the Reactor Safety Bibliography prepared for the Reactor Safety Conference held at New York City on Oct. 31, 1957. It is not an exhaustive review of the published material on reactor safety but includes 223 selections from reports and published literature as a guide to some of the more recent and relevant material. (J.E.D.)

None

A description is given of the valve operating system for the PWR. The valves served by this system are a component pant of the following systems: reactor coolant system; pressurizer and pressure relief system; coolant discharge and vent system; and failed element detection and location system. (W.L.H.)

None

None

State, Government, and ASME Codes are given for the radistion exposure, waste disposal, piping, and pressure vessels for the PWR reactor plant. (W.L.H.)

None

Progress is reported on the gross solubility of U in digestions of Mallinokrodt feed materials, studies of variables affecting U purity in a TBP hexane extraction cycle, low-acid flowsheet for TBP--hexane extraction process based on a 440 g U/liter in lM HNO/sub 3/ digest liquor, hacking studies in the pilot plant pumperdecanter system, recovery of U from residues from the dingot process, lowering the H level in dingot metal, forging of dingot bar stock, dingot extrusion, fubrication of UO/sub 2/ fuel elements, and the determination of H content of derby and ingot metal. (W.L.H.)