This document contains information about the sampling program at Columbia River during May 5, 1944. Topics discussed include: securing representative samples; analysis of the samples looking at temperature, bacteriological content, dissolved oxygen, and physical tests; and the method and equipment used in the sampling procedure.

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A scheme was proposed whereby the third and second uranium cycle salt wastes in the Redox plant are combined, stripped, evaporated, and then returned as scrub to the first (and possibly second) cycles as scrub, operating as a dual scrub column. It is the purpose of this report to study this proposed method of back-cycling, and to investigate other methods of reducing chemical and waste storage costs.

The attached unclassified article was prepared for publication in Civil Engineering. It describes construction techniques and equipment used in processing, prepacking, and grouting heavy aggregates used in the construction of the K-reactors.

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Under simplifying assumptions, an expression is obtained relating the integrated kinetic energy transferred to moderator atoms to the thermal neutron exposure in adjacent fuel. Reactor-dependent factors are explicit in the expression which make it possible to compare graphite contraction data from different reactors or to estimate graphite damage in a new reactor based oil observed damage in existent reactors. Graphite temperature, which may be an important factor in graphite contraction, is not considered as one of the variables in this report. Also, the damage dependency on neutron energy is not dealt with in great detail because of the relatively unknown facts in this regard. A particular application of concern at the present is to determine the pertinent factors relating to fast neutron exposure in the NPR to assist in determining the integrated damage over the life of the pile.

To provide flow increases in excess of the current water plant capacities at the old reactors, a short-range water modification program has been proposed by Facilities Engineering Section. The proposed program outlined by Facilities Engineering Section includes increased 181 and 183 building pumping capacity at B, D, and H areas, a new filter for F area, and larger impellers for the 190 building pumps at H area. It has been estimated that beneficial use for this proposed increased water plant capability can be obtained by the late fall of calendar year 1962 if prompt project approval can be obtained. In order to obtain an economic benefit from the proposed water plant capacity increases, methods of increasing flow through the reactor must be devised. Initially, various publications discussing this project inferred that rear Parker fitting reaming and installation of larger diameter rear-face pigtails were the only methods by which reactor flow increases could be economically justified. Hence, initially, acceptance of the short-range modification program appeared dependent on Parker fitting reaming and larger rear-face pigtails. Since the possibility of these two modifications will require further investigation, it is desirable to briefly explore alternate methods for increasing reactor flow so that the acceptance …

Metallic thorium uranium fuel elements continue to show excellent irradiation performance in high temperature pressurized water coolant. Volume expansion measurements made after 2.1{times}10{sup 20} fissions/cm{sup 3} (6200 MWD/T) at fuel temperatures above 500 C shows no indication of fission gas-in-duced swelling. Analysis of fuel swelling data from tubular elements shows apparent effect of geometry (restraint) on both low temperature volume expansion and the temperature at which accelerated volume expansion initiates. Evidence of grain boundary tearing has been observed in tubular metallic uranium fuels irradiated in 1600 pos water coolant. Volume expansion due to two types of structural damage have ben observed uranium - 2 w/o zirconium alloy irradiated to 0.25 a/o burnup at temperatures up to 550 C.

The specific impulse achieved in a pulsed rocket engine augmented with a fissioning nuclear bomb could be greater than that of any continuous flow engine. To a certain extent, this increase in specific impulse would be obtained at the expense of motor weight and average thrust. This paper considers the first of these limitations, motor weight, and estimates the highest effective specific impulse to be expected from a nuclear-pulsed rocket motor with respect to the weight of the motor.

Alum is used as the coagulating agent in the water treatment process at Hanford. The bicarbonates present in Columbia River water react with the alum to form a loosely knit aluminum hydroxide molecule. Finely divided particulate matter and large organic molecules present in raw water are adsorbed by the floe particles. Partial is accomplished by settling in the basins; however, gravity filter beds remove the greater part of the suspension load. A polyacrylamide is added to the filter inlet stream to form a binding net around the floe particle. The floe particle is now more resistant to shearing and a greater amount of small particles are retained in the filter bed. The objective of this test was to re-capture parent isotopes of phosphorous and arsenic that had passed through the filters by secondary alum coagulation. The size and density of the floe particle would be increased by employing bentonite for the nucleus. The larger particles should now pass through the reactor with minimum residence time for activation. A polyacrylamide would again be used to net or toughen the floe particle.

During the week of March 1, 1965, KW Reactor shut down with indications of a tube leak. Leak testing during the shutdown indicated a front Van Stone flange leak on tube 3065 and a suspect internal leak on tube 3075. During the tube removal process, there was indication of Zircaloy embrittlement on both tubes. Subsequent metallographic examination of samples taken from these tubes indicated the presence of case hydriding on the internal tube surface extending from approximately the end of the active fuel corn to the rear Van Stone flange. Vacuum analysis of selected samples revealed the total hydrogen concentration, including the hydrogen present in the hydrided layer, ranged from approximately 50 ppm at the end of the active charge location to approximately 1300 ppm at the rear Van Stone flange, Since examination of these first two Zircaloy tubes removed from KW Reactor, two additional tubes have been removed from KW Reactor, two tubes have been removed from KE Reactor, and one C-size Zircaloy tube has been removed from C Reactor. The presence of hydriding has been observed on the seven Zircaloy-2 tubes removed to date. It is the purpose of this document to review in some detail the data …

Reactor fuels, reactor engineering, radiological engineering, process technology, and operational physics progress is reported for irradiation and testing at the Hanford production reactors.

A half reactor test was initiated at B Reactor on February 1, 1967, to determine whether the concentration of P{sup 32} and As{sup 76} in the reactor effluent water would be reduced by the addition of activated alumina in the water treatment process. This test was prompted by the reported effectiveness of activated alumina in sorption of phosphates when water flow is through a packed bed of this material. Although direct feed of material would not be expected to be as effective, testing of this possible approach appeared warranted. This report summarizes the results of this test. Samples taken from each effluent riser during reactor operation indicated no improvement in either As{sup 76} or P{sup 32} performance. This comparison is shown below with a complete tabulation of daily values included as Attachment 1.

Progress is reported on the following: well conditions; perforating and cementing; temperature-depth plot; slotted liner, well head and auxiliary equipment; well testing and analysis program; well monitoring during standby; environmental assessment; time schedule; and budgets. (MHR)

Beryllium-copper alloys should be considered toxic materials and proper controls must be used when they are machined, heated, or otherwise fabricated. Air samples should be taken for each type of fabrication to determine the worker's exposure and the effectiveness of the controls in use. It has been shown that aerosols containing beryllium are generated during the four methods of fabrication tested, and that these aerosols can be reduced through local exhaust to undetectable levels. Considering the acute, chronic and possibly carcinogenic effects of exposure to beryllium, effective controls should be required because they are feasible both technologically and economically. The health hazards and control measures are reviewed.

A redesign of the LOFT instrument penetration necessitated a reanalysis of the thermal conditions existing in the nozzle and flange during a Loss of Coolant Experiment (LOCE). The maximum temperature gradient existing in the instrument flange will be used to determine the thermal stresses and maximum number of allowable cycles for the instrument flange. Based upon the specification and thermal conditions predicted by RELAP4/MOD5, the maximum temperature gradient through the flange will not exceed 216/sup 0/F. The thermal conditions predicted by RELAP4/MOD2 for the nozzle head penetration assembly were less severe than those used in the original thermal-stress analysis, so only the flange was analyzed here. If the thermal stresses are marginal with the 216/sup 0/F ..delta..T, a more detailed analysis should be done as the heat slab model used in RELAP is only one dimensional. Conservative hand calculations were performed for a heatup rate of 100/sup 0/F per hour and it was determined that the worst temperature gradient through the flange will be less than 81/sup 0/F.

The FRS is a pool structure and enclosing building constructed in 1966 for storing spent nuclear fuel. The enclosing building was not analyzed. The pool structure's responses to operating loads, seismic excitation, and an accidentally dropped cask were determined. Locations in the FRS pool were identified where structural strength would be exceeded in the event of an earthquake of 0.2 g maximum ground acceleration or an accident in which a cask dropped from the maximum height of the crane hook used to maneuver it. 25 figures, 4 tables.

The cyclone incinerator was operated throughout the past quarter, generating additional data on system characteristics, equipment life expectancies, and by-product generation. Several changes in the incinerator system are in various stages of completion. The lid assembly, secondary chamber, and expansion unit for the new exhaust equipment are nearly ready for installation. A new heat exchanger has been installed in the scrubber system. An ash handling system has been designed for possible future addition to the system. Continuing studies will determine the best delivery mechanism for continuously feeding the cyclone incinerator. Preliminary investigations are being conducted to select an independent system to treat incinerator scrubber solution for recycling and to remove salts and sludge for disposal. Metal samples of two possible materials for incinerator construction were examined for corrosion degradation suffered at the incinerator exhaust outlet. Controlled experiments were conducted on the pressed ash-cement pellet matrix to define compressive strength, mechanical stability, density, and effect of curing environment (wet cure and dry cure). Leachability studies were initiated on pressed sludge/cement matrix in distilled water at ambient temperature. Compressive strengths of sludge/cement pressed matrix samples were investigated. Physical and chemical attributes of incinerated ash were evaluated in relationship to the ash/cement matrix.

The laboratory cyclone incinerator, which started operation in January, 1978, has been developed to study the effects of burning feed containing radionuclides other than /sup 238/Pu. These isotopes must be removed from the off-gas during incineration. Preliminary data from early runs show that the combustion efficiency of the incinerator can still be improved. Controlled experiments were conducted on the pressed ash-cement pellet matrix to define compressive strength, mechanical stability, density, and effect of curing environment (wet cure and dry cure). Leachability studies were initiated on pressed sludge/cement matrix in distilled water at ambient temperature. Compressive strengths of sludge/cement pressed matrix samples were investigated. Physical and chemical attributes of incinerated ash were evaluated in relationship to the ash/cement matrix. 7 figs., 6 tables.

This report disucsses the development of on-line state and parameter estimators used to analyze the structural response of buildings. The estimator/identifier is an extended Kalman filter (EKF), which has been applied with great success in other technological areas. It is shown that the EKF can perform quite well on simulated noisy structural response data.

TMX experimental data on ambipolar potential control and on the accompanying electrostatic confinement are reported. New results on the radial dependence of the central-cell confining potential are given. Radial and axial particle losses as well as scaling of the central-cell axial confinement are discussed.

The design of the Target Fabrication Tritium Laboratory for deuterium-tritium fuel processing for laser fusion targets has been accomplished with the intent of providing redundant safeguard systems. The design of the tritium laboratory is based on a combination of tritium handling techniques that are currently used by experienced laboratories. A description of the laboratory in terms of its interrelated processing systems is presented to provide an understanding of the design features for safe operation.

A hydrologic test system has been designed to measure the intrinsic permeabilities of individual fractures in crystalline rock. This system is used to conduct constant pressure-declining flow rate and pressure pulse hydraulic tests. The system is composed of four distinct units: (1) the Packer System, (2) Injection system, (3) Collection System, and (4) Electronic Data Acquisition System. The apparatus is built in modules so it can be easily transported and re-assembled. It is also designed to operate over a wide range of pressures (0 to 300 psig) and flow rates (0.2 to 1.0 gal/min). This system has proved extremely effective and versatile in its use at the Climax Facility, Nevada Test Site.

A detailed study of the low beta insertion for the B0 experimental area has been carried out and is described below. This insertion is similar to the Type C low beta previously report, anti p Note 169, although some changes have been made to the quadrupole lengths and positions. This insertion is designated Type E. The purpose of the study was to see if it is possible to turn the insertion on in a smooth and continuous manner and tune the insertion to a value of ..beta..* of less than one meter while maintaining the overall tune of the j Tevatron to a constant value. This was found to be possible. An examination of chromaticity corrections for the Tevatron with the low beta insertion on in various configurations was also undertaken.