The objective of this test is to establish that scavenging of first-cycle wastes in the Bismuth Phosphate Plant will give a supernatant liquor, after the precipitate settles, that may be routinely cribbed. This test will also perform the functions: establish an effective scavenging procedure, shakedown the pH monitor, and train operational personnel. This document discusses test procedures and results.

This report describes the direct essential material requirements for processing a standard run through the precipitation separations process in effect on August 1, 1954. Flow sheet conditions are based on a starting maximum batch size of 300 grams of product at a uranium irradiation level of 215 MWD/ton. The essential material requirements are those used to process with 2.5 grams of Bismuth per liter in Extraction, First Decontamination Cycle volumes at 56% of the September 1, 1946 standard, and Second Decontamination Cycle through the Lanthanum Fluoride Product Precipitation volumes at 49% of this standard.

Tube 1794-C was removed from the pile as a leaker on July 15, 1954. The tube had been in-pile since startup and had contained a charge of 32 ``C`` metal slugs just prior to discharge. The tube was slit and examined at the 105-DR underwater viewing facility by Pile Coolant Studies tube examination personnel. A report is made of the examination of tube 1794-C which revealed areas of severe pitting damage. This damage was apparently caused by cocked slugs abrading the tube. The attack was great enough to cause perforation of the tube at about 27 feet from the rear Van Stone flange. Examination of the slugs showed that a considerable number had been cocked. Evidence of severe tube scarring and rib grooves was found on the slugs. Strikingly similar examples of pitting and grooving were observed on flow laboratory minitubes and slugs exposed in high velocity water. It is concluded that the damage observed both in- and ex- pile was caused by the chattering of misaligned low density slugs in a high velocity stream. If the number of in-pile occurrences of this attack becomes excessive it is recommended that the water flow rate in tubes containing ``C`` metal slugs …

This experiment was designed to furnish data on the quantitative relationship between exposure of enriched uranium metal to thermal neutron bombardment and the subsequent release of gaseous fission fragments from the metal. Studies of data obtained from the in-pile phase of the KAPL Fission Gas Experiment indicate, neglecting startup and shutdown transients, that gaseous fission fragments generated within a 6-mill foil of uranium metal maintained at an operating temperature of about 450 C are released from the foil nearly as fast as they are produced.

This report covers the preliminary data obtained in a metallurgical study of the three enriched uranium slugs which ruptured in the 100-C Pile. The three slugs were from PT-105-532-A2, ``Irradiation of Enriched Uranium Slugs,`` a test conducted by Pile Technology for the purpose of studying the effects of high specific powers in uranium slugs. The uranium used in this test was enriched to 1.75.

This is the second of a series of documents issued quarterly. The documents present, for critical examination by management and for the information of related groups, that portion of the future 100 Area technical program which relates directly and more or less immediately to the Technical-Manufacturing efforts to increase both power levels and production. An attempt is made to describe and justify the key production tests planned for the following six month period. Only those tests necessary for the relief of technical and process limitations and vital to the slug improvement program are included. Best estimates of changes in current Process Specifications during the ensuing six months are also given. To further longer range planning, power level forecasts based on foreseeable changes of technical limits and scheduled physical changes of the water plants and reactors are extended several years into the future.

Portions of the Hanford Reservation in 1954 had significant particulate contamination from the Redox process. This paper is about the methods used to decontaminate the Reservation. The two methods are decontamination and access control. A general description of the ideas and benefits of each method is given. (MB)

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A description is given of the Sodium Reactor Experiment (SRE) facilities and program of objectives. The hazards associated with equipment failures and malfunctions, personnel errors, natural causes, and operation are evaluated (C.J.G.)

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Every type of thermal insulating material tested showed attack in varying degeces. Many specimens which had been cured at 1000 deg F, with no color change, did show drastic changes at 950 deg F due to the action of sodium. The materials showing the least disintegration and greatest preservation of mechanical properties were Superex paste and Eagle-Picher mineral wool. The uncured Superex Block did not hold up as well as Superax paste, presumably due to the presence of water of crystallization; after curing, the results were similar to that of the paste. The refractory clays showed the greatest degree of destruction. The time element is of vital importance, since a long perfod of contact with liquid sodium would presumably result in complete destruction of every specimen tested. (auth)

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This paper briefly reaccounts principal progress items addressed at a April 1954 meeting on ruthenium release and abatement measures for the Redox Plant at the Hanford Engineer Works. (JL)

To determine, by test, the feasibility of decreasing the time requirements to prepare the aluminum clad uranium slugs into uranyl nitrate solution suitable for the separation of plutonium from uranium in the extraction step.