The following document is a note describing the building process of an improved nuclear density gauge in comparison to previous gauges, within the interval of July 1 to August 1, 1959.

This Program detailed in this report is related to the Product Development, Palmolive, and Non-Production Fuels Programs under New and Special Products and Processes Category where the prime separations plants supply raw materials or processing support of these other programs. Likewise, Increased Plant Return Program items affecting the Purex, Redox, and UO{sub 3} Plants must be integrated with the Continuity of Operations Program. Since the primary separations plants feed the 234-5 Facility, the 234-5 Program is also related to Continutiy of Operation.

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This test is designed to accomplish two primary objectives: (1) to attempt to verify ex-reactor corrosion data which indicated improved corrosion resistance of cast blank X-8001 alloy material compared with wrought blank, and (2) to attempt to verify the resistance to groove pitting type of corrosion attack previously observed on M-388 components. Ex-reactor tests of cast blank M-388 alloy in autoclaves using water as the corrosive media up to 360 C, and in flow loops up to 120 C have indicated that the corrosion resistance of the cast blank material is equivalent to, and probably superior to the corrosion resistance of wrought blank material. Metallographic examination of this material indicated a more uniform nickel dispersion in the aluminum as a probable explanation of this performance. The sporadic occurrence of severe groove pitting has seriously challenged the use of X-8001 nickel aluminum alloy as a fuel element cladding material. Although the actual cause of the groove pitting has not been determined, non-uniform dispersion of the nickel in the alloy is suspected. The cause of the non-uniform nickel dispersion or segregation has been located and virtually eliminated by removal of additional aluminum (scalping) from the ingots prior to fabrication of the components.

The purpose of this report is to provide scope and justification for the installation of two new 16,500 gpm, 150-foot head pumps in the 181-C building in order to furnish sufficient additional water to increase production at 105-B and to supply the entire normal export demand from B Area. A minimum of 11,000 gpm will be required to be transferred from the 183-C reservoir to the 183-B clearwell via the cross-tie line during the adverse turbidity period when the I&E program is in effect at 105-B. It is contemplated to transfer 15,000 to 20,000 gpm so as to provide the necessary water for this increased flow at 105-B and to reduce the flow through the existing 183-B filters. It is apparent that the pumping capacity at 181-C is not adequate to supply this extra water at 183-C unless all export pumps are used to pump water to 183-C. If this increased demand were met by using the export pumps, the 100-D Area would have to supply most of the export demand to the 200 Areas which is anticipated to be 12,000 to 15,500 gpm. After the new expected I&E flows are achieved at 105-D and 105-DR, D Area will have …

An X-8001 clad, I & E natural uranium fuel element irradiated in tube 2762D to 886 MWD/T was discharged in February 1959 and sent to Radiometallurgy Laboratory for examination at the request of Irradiation Processing Department. After discharging tube 2762D which was loaded with X-8001 clad fuel elements, a fuel element (KL018D) was observed to be very badly pitted. Visual and photographic inspection revealed the pits had penetrated into the AlSi layer. The pitting appeared as the result of erosion-corrosion as there was no evidence for intergranular or transgranular corrosion and no mechanical deformation. Chemical analysis for %Ni and Fe indicated normal concentrations.

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Abstract: A study has been made of the source, acceleration, and neutralization of ions for application to space propulsion. A summary is made in this paper of some of the most important problems in this area and their solutions.

Review of a study regarding a lid-tank shielding facility's properties, including fast-neutron and gamma dose rates and thermal-neutron fluxes, which were mapped in a symmetry plane. The removal cross section of gadolinium was determined through comparison with various other materials.

The 107-B retention basin was constructed in 1943--44 as part of the original reactor installation. Thermal stressing has caused extensive cracking of the concrete walls and leaking at cracks and joints, requiring repeated maintenance including a major repair program in 1952--53. Although a major repair or replacement program will eventually be necessary, existing basin leakage does not require immediate action, other than periodic control effort, with one exception. Effluent from 107-B leakage is flowing into the 181-B river pumphouse forebay, measurably increasing the temperature of the raw water and raising the question of continued stability of the building foundation. A basic inadequacy also exists in the inability to dispose of undesirable effluents other than to the river. The unique situation of B Reactor adjacent to the C Reactor effluent system permits consideration of improving the effluent disposal situation in this one area with minimum capital investment. The purpose of this report is to provide the scope for a project proposal for interim effluent system modifications in 100-B Area only. This will avoid future production losses and improve effluent disposal capability during resolution of a more permanent solution to the overall problem of effluent routing and treatment.

Discussions are given of the characteristics of fission-source plate, graphite reactor, and pool-type reactor facilities applicable to development studies of minimum weight shielding materials. Advantages of a proposed SNAP dual-purpose shielding facility are described in terms of a disk-shaped fission-source plate, reactor, and building. A program for the study of advanced shielding materials is discussed for materials and configuations to be evaluted with the fission-source plate, the testing of the prototype at high-power levels, and full-power tests on the actual reactor.

In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.

An improved heat sink for space vehicles was proposed in ORNL-CF-59-1-21. Subsequent work on the problem has indicated that there is a substantial probability of a puncture of such a radiator by meteors. To meet this problem a modified geometry has been evolved for which the probability of a meteor puncture should be reduced by a factor of at least 100 relative to the radiator of the original proposal at the expense of an increase in radiator weight of possibly 30%. This memorandum outlines the approach to the problem and a series of similar promising solutions.

A lid-tank shielding facility, simular to the one in operation at Oak Ridge, has been constructed and is in operation at Battelle. This facility was descnibed in BMI-1291. The fast-neutron and gamma dose rates and thermalneutron fluxes were mapped in a symmetry plane of the shielding tank. Fast-neutron and gamma dose rates were raeasured behind a series of shielding plugs along a line in the water perpendicular to the fission-plate center. The plug materials included aluminum, iron, lead, titanium, and gadolinium. In order to use small- diameter plugs the effective diameter of the fission plate was reduced for these experiments by placing an iris between the thermal column and the flssion plate. The purpose of the test was to determine the removal cross section of gadolinium by comparison with other materials, using a small amount of gadolinium. The removal cross section for gadolinium is about the same as for lead. Experiments were conducted on ordinary and enriched LiH slabs 4 to 32 in. thick. Fast- neutron and gamma dose rates in addition to thermalneutron fluxes were measured on the water center line behind the slabs. (auth)

Presentation at the National Western Mining Conference of the Colorado Mining Association, Denver, Colorado, February 7, 1959. Thank you for your invitation to discuss here today some of the aspects of nuclear explosions in mining and mineral industries. I should like this afternoon to dwell briefly upon: (1) The phenology of a nuclear explosion underground. What happens; with what energies are we concerned, and what may be the scientific and industrial results of such an explosion? (2) The safety or radiological hazards involved. If mining men hope someday to use this new and potentially useful source of packaged power, what are some of the problems we may face? First let me emphasize that the nine underground test explosions thus far have resulted in a wealth of data and interesting information which prove that radioactivity and radioactive fall-out can be completely controlled, that seismic effects are relatively minor, that appreciable amounts of heat and shock are generated, that this power might be utilized to serve a useful purpose and that the debris in an explosion area can be worked soon after the detonation.

Activities of the Explosives Group of the Lawrence Radiation Laboratory for the months of September, October, and November 1958 are presented.

The relatively high heats of combustion of CHN compounds containing multiple bonds has prompted an investigation of the possible use of these compounds as explosives components. Three possible systems are being considered for testing in the small scale plate push apparatus: acrylonitrile-tetranitromethane, propiolonitrile-tetranitromethane and dicyanoacetylene-tetranitromethane. Samples of propiolamide and acetylene dicarboxamide, intermediates in the synthesis of propiolonitrile and dicyanoacetylene respectively, have been prepared and their infrared spectra determined. The heats of explosion of uncased charges of bis-trinitroethylnitramine has been performed. A program to investigate some properties of high explosives at microwave frequencies is being undertaken. Heterogeneous explosives consisting of metal-loaded organic explosives were also tested. Synthesis work was performed on nitrogen-fluorine compounds, boron-hydrogen-nitrogen compounds, reaction of hexachloromelamine with chlorinetrifluoride, and nitration studies.

The moderator fluid will be injected into the PRTR calandrin through injectors located between the shroud tubes and at the bottom of the calandrin. It is important that the size and arrangement of the injectors be such that complete mixing of the moderator will occur and prevent hot sports from forming in the moderator. Such hot spots could lead to undesired changes in the moderating characteristics due to boiling within the moderator. Also of importance is the requirement that the injector should not produce excessive turbulence at the moderator surface thereby complicating moderator level control. To determine the extent of moderator mixing within the calandrin, experimental studies were made employing a full scale PRTR calandrin mockup.

The small amount of irradiation tenting experience on the plutonium-aluminum type elements planned for the Plutonium Recycle Test Reactor (PRTR) has made such testing of great importance. The high temperature pressurized recirculating water 1706 KER facility is one possible place for conducting investigations of the irradiation behavior of this type fuel element. To obtain the maximum information from the in-reactor testing and to detect possible problems, out-of-reactor test both at room and anticipated operating temperatures must be made. Room temperature pressure drop measurements and high temperatures performance of two prototypical fuel element designs proposed for KER testing are reported in this document.

Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.

The effect of the (n, 2n) and (n, o<) reactions on the neutron economy of a beryllium moderated reactor is investigated.

A preliminary study of dispersing agents for thorium oxide has been completed and several of the dispersants have possible uses. Also many of the industrial dispersing agents tested are not usable with thorium oxide due to induced behavior causing balling and caking. The effects of nitric acid concentration have been observed to also effect each dispersing agent.

The purpose of the test was to observe the extent and location of corrosion, crud deposits and defects in components of the primary fluid system and its auxiliaries. This observation will allow an estimate to be made of the future behavior of the affected parts. The test also provides for obtaining corrosion products and crud samples for analysis as necessary for planning remedial actions. This test was limited to the 1D Main Coolant Pump which failed November 3, 1958. The pump failed after 2234 hours of operation on "fast" speed and 887 hours at "slow" speed. An inspection for corrosion was not conducted but smear samples were taken and a radiochemical analysis made. This analysis showed the following isotopes were present in the smear sample: Co38, Co60, Fe59, Mn54, Hf191 and Zr95. The upper and lower radial pump bearings and journals were severely scored and galled while the thrust bearing and runner appear to be in good condition.

The purpose of the test was to obtain performance data for the main coolant pumps on fast and slow speed at various coolant temperatures. The 1A, 1B and 1C pump performances on both fast and slow speed were approximately as shown in the manufacture's predicted performance curve. The 1D pump performance was below the manufacturer's predicted flow efficiency, line current and hydraulic horsepower on both fast and slow speeds.