This report has been prepared to review the status of design for buried waste line and presents the major factors involved in support of the conclusions. This report is the second in a series reporting on the general subject of underground corrosion. The first on cathodic protection of waste lines noted the technology of stainless steel and its effect on existing waste line and recommended continued use of the cathodic protection. Experience with buried stainless pipe had shown that, unless protected, such installations are subject to severe pit corrosion. As designs developed the use of encasements has become a standardized approach. This discussion will evaluate this trend.

Equations are developed for the computation of MPC's for radioisotopes assuming the excretion or retention to follow a power law rather than an exponential law. Computations are made for four isotopes on which some human data are available. Uncertainties in the initial data due to the use of intravenous injection to obtain the primary data, the definition of retention and the effects of age and diet are discussed.

The purpose of this report is to present the information obtained relative to the characteristic adsorption of radioisotopes in a long (forty feet) laboratory soil column treated with a high salt, process waste of high activity density. The movement of adsorbed cations in a soil column subjected to prolonged leeching by water also was determined.

Report that presents and interprets data taken from previous tests involving gas-lift circulators and then correlates the data for the purpose of design and operational improvements.

As potentially suitable alternate methods of installing closure plugs in cored slugs, four different schemes were considered. One of these schemes, whereby a flat chamfered uranium disc is crimped into a counterbored recess at each end of the bare slug after pickling, was developed to a workable state, and partially evaluated prior to reassignment of the job to another group. From the results of initial evaluation tests, this process appears to provide leak-free core closures and offers economic benefits that make it attractive as a production method, should cored slugs be adopted as standard.

Ten materials in which gold was alloyed with copper, silver, graphite, platinum, nickel or zinc (compositions given in Table 1) were evaluated in this study. Corrosion tests to determine the resistance of the alloys to boiling 60 to 65% nitric acid showed that with the exception of an alloy containing 51 wt % gold and 49 wt % graphite (Gold Graphalloy 811) which dissolved in 48 hr and an alloy containing 90 wt % gold and 10 wt % graphite which lost 2.3 wt % in 240 hr the alloys were essentially corrosion resistant.

An Alpha Scintillation Probe for use with the HAPO Cart Poppies has been designed to replace the air proportional probes presently used. The new probe has an average geometry of about 15 or 16 percent over an effective probe area of 23.4 in². Stability of operation under normal conditions of vibrations, humidity and temperature are inherent qualities and the average background count is stable at about two counts per minute. The high voltage used is in the order of 1,200 to 1,250 volts with a current requirement of 100 microamperes.

The water plant for a high temperature reactor must be capable of providing several purities of water to the various components of the installation. The actual treatment methods will depend on the location and size of the reactor, the size and sources of the water and the ease of disposal of radioactive wastes. This document examines the needs for the various water purities. It also defines the area of future work to provide the information necessary for the design of water plants for high temperature reactors or for the conversion of existing reactors to recirculation cooling.

The surfaces of cold rolled, half hard, nitric acid treated, autoclave etched, 2S aluminum coupons were studied by optical and electronoscopic methods, before and after exposure to hot water alone and hot water and neutron bombardment. The non-exposed aluminum surfaces have a characteristic pattern which is absent in the exposed coupons. All of the exposed coupons were corroded. In general the coupons exposed to the higher flux intensities of irradiation were more severely corroded than those exposed to the lower flux intensities of irradiation or to the hot water alone. Representative photo-and electron micrographs illustrate the various types of surface structure observed on the control and experimental coupons.

A design study has been made of a graphite superheating reactor, a graphite moderated reactor with a heat rating of 305 Mw which produces superheated steam. It is designed for the production of plutonium and electrical power or for the production of electrical power only. The fuel elements for dual- purpose operation are U metal, while for single purpose action, they are uranium oxide. The fuel elements are cooled by a 7-pass system in which preheated water enters the bottom of the first pass and is discharged as superheated steam at the top of the seventh pass. The reactor control consists of shim control by the gas system, vertical gas-cooled control rods, vertical safety rods, and a ball safety system. Rough cost estimates indicate that the capital cost of the reactor should be comparable to other reactors of similar heat output.

Fillerwelding is a fusion welding process that provides for the automatic addition of controlled amounts of fillerwire during inert-gas-shielded tungsten-arc welding. Fillerwelding aluminum jacketed fuel elements has been successfully demonstrated and is being used on a routine basis. This manual was written to provide the necessary information to operate and maintain the fillerweld equipment.