Shielded enclosures equipped with viewing devices and remote-hauling equipment for use in experiments and processes involving radioactivity are referred to as hot cells. The hot cell includes the biological shield enclosing the working space, viewing devices, special ventilating equipment, and special equipment for use in the hot cells, such as manipulators, cranes, machine tools, and measuriag devices. A hot cave is the same as a hot cell. A junior hot cave is a small-sized hot cave. A summary is presented of pertinent data on hot cells in use at various AEC installations. (C.H.)

This bibliography is a compilation of titles to unclassified reports, journal articles, and conference papers. The individual papers are divided into sections according to the year in which they appeared. (M.H.R.)

The objectives of the conference were to accomplish an interchange of information and study the determination of contact resistance. The effect of contacts on AEC production problems is discussed. Otber discussions are presented one applications of contact devices, present testing criteria, materials and process variables, process controls, and future development plans. (T.R.H.

The status of development studies being conducted on a pebble bed power reactor is outlined. The items discussed are fuel element manufacture, stability, and reprocessing, and component development. (D.L.C.)

Originally issued as S and P 1963A, Parts I and II. A design and feasibility study of a pebble bed reactorsteam power plant is presented, The reactor design which evolved from this study is a 125 Mwe heliumcooled two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Nuclear characteristics, costs, etc., are given. (W.D.M.)

The specifications for the D1G reactor pressure vessel and accompanying insulation, shield tank, thermocouples, test heads, fixtures, tools, and repair parts are given- (T-R-H-)

The combined attack of HNO/sub 3/ and HNO/sub 2/ on TBP-kerosene solvents used in the Purex Process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination. (auth)

Unclassified Engineering Materials List, TM-4100(lst Rev.), is a catalog of available U. S. Atomic Energy Commission unclassified engineering drawing materials on the peaceful applications of atomic energy. The engineering literature described in this publication includes drawing, specifications, photographs, bill of materials, cost analysis, design criteria, psrts lists, and supporting textual data. This consolidated list m- cludes all materials originally announced in TM-4100, January 1957, and TID-4100, Supplement 1, July 1957, and additional engineering data received and cataloged by TlSE after the original issuances. The entire publication, TID-4100 lst Revision Supplement 1, is devoted to the Shippingport Pressurized Water Reactor. (W.L.H.)

None

In this document it is proposed to describe the plant site and to outline the nature of the pile in order to show the specific design and layout requirements for the production of plutonium by nuclear synthesis. The selection of the plant site involved a number of special considerations. An essential requirement was a large dependable supply of relatively pure water that remains at a fairly low temperature throughout the year. A large source of power was required to circulate the tremendous quantities of water. The potential dangers connected with the high energies of the nuclear reaction and the formation of a large quantity of radioactive by- products required large distances between each operating section of the plant, and between the plant and main rail and highway routes. The plant site layout and reactor areas are discussed in the first part of the chapter, followed by a functional description of the more essential pile components. The chapter concludes with a discussion of reactor instrumentation. 24 figs., 2 tabs.

The results of laboratory studies on sodium carbonate ion exchange are shown. The effect of salt concentration, uranium concentration, and possible interference with ion exchange from vanadium, molybdenum, sulfate and chloride are discussed. Various elution systems and the effect of residual uranium are described. A short discussion of ammonium carbonate ion exchange is also presented. (auth)

A pile oscillator was designed, constructed, and operated at the Battelle Research Reactor. This pile oscillator cycles a specimen and a standard in the same container through an annular ion chamber located in the thermal column. This almost simultaneous oscillation of the standard and specimen eliminates errors caused by power drifts or fluctuations. The use of a continuous graphite rod for the container or carrier reduces undesirable scattering effects of the carrier. The oscillator was calibrated using the cross section of gold foil as a standard. Effects of geometry on measured cross sections were investigated. In general, larger samples gave higher apparent crosssection values than thin foils of comparable cross sections. Most measurements to date were made on powdered-metal samples. Values obtained at Battelle are presented and compared with values from Oak Ridge on similar samples. At present the sensitivity of the oscillator is limited to total absorption cross sections on the order of 1 mm/sup 2/ for accurate crosssection data. The limit of the accuracy of the measurements is approximately the accuracy to which the absorption cross section of the standard sample is known. An analysis of the errors indicates that cross sections on the order of 1 mm/sup …

This report describes the development of work that began as an investigation of photosynthesis and that continues in this direction, but which has as a new product some entirely strngly results. Photosynthesis, the process upon which all life on earth today is ultimately dependent, achieves the conversion of electromagnetic energy from the sun into chemical energy in the form of plant material by the reduction of CO{sub 2} from the atmosphere with the liberation of O{sub 2} to the atmosphere. It has been possible to describe in some detail the way in which the plant accomplishes the reduction of carbon dioxide, using radioactive carbon as a tracer. The status of the present knowledge, and how they attained it, together with some prospectus of the future and what we can look forward to, is the principal theme of this discussion.

A formal mathematical description of the time dependence of activity in the maln coolant loop of a pressurized water reactor resulting from the discontinuous release of core contalned fission products is developed. The description accounts for the deposition, re-solution, and demineralization of activities due to one, two, and three member mass chnins- A description of the IBM-650 WOLONTIS Code No. S0168, which numerically evaluates the various activities discussed, is given in the appendix along with the input data and results for a pair of exemplifying problems. (auth)

Results are given from studies on: mechanical properties of Zircaloy-2; preparation of Al--U alloys; effects of N, Ca, Zr, and Mo on electrical properties of UO/sub 2/; effect of chloride, fluoride, and sulfate contamination on corrosion of type 304ELC stainless steel in boiling HNO/sub 3/; density of Mallinckrodt slag and MgF/sub 2/-base materials; development of gamma-phase U alloys; preparation of U--Nb alloys; oxidation of Nb and Nb alloys in dry air at 1000 and 1200 deg C; thermal expansion of UBe/sub 13/ and UC; phases and compositions in C --N--U system; creep of arc-cast Ta during exposure to high- temperature Nas pressure bonding of PWR fuel platess evaluation of UC as reactor fuels and fabrication of UO/sub 2/ fuel pellets for NMSR loop tests. (For preceding period see BMI-1259.) (T.R.H.)

A study has been made of the radiation received by staff members of the 60-inch cyclotron for the period from 1953 to 1957 and of the radiation environment in the target area. The nature of the operations has caused workers to receive an average amount of radiation that was within the formerly acceptcd limits and in addition is less than the present maximum recommended by the AEC. Namely, the Maximum permissible Dose (MPD) to the most critical organs, accumulated at any age, shall not exceed 5 rems multiplied by the number of years beyond age eighteen and the dose in any thirteen consecutive weeks shall not exceed 3 rems. There has been a yearly decrease in average exposure however, and constant improvement of techniques lessens the amount of radiation received. (auth)

The study of the toxicity of radium and radium decay products was continued. Special emphasis was placed on the acquisition of data on patients selected by record of exposure. Data are tabulated on the radium body burden of about 40 individuals. About half the measurements were made on living persons and about half on tooth or bone specimens. Case history summaries and all available medical data are summarized for persons under study. An investigation of the gamma shielding properties of dunite was continued. Design modifications and calibration of radiation detection instruments are discussed. (For preceding period see AECU-3504.) (C.H.)

None

Shielding Computer Program 04-0 is available for computing reactor- shield weight and fast neutron and gamma ray dose rates in and around complex resctorshield assemblies. Reactor and shield geometries are described by combinations of regions formed by rotating rectangles or trapezoids about the reactor axis or by translating rectangles parallel to the reactor axis. Compositions are expressed as volume fractions for each material in the reactor- shield assembly. A cylindrical coordinate system is used to describe the location and dimensions of a volume source. Source distributions are assumed separable and may be described by cosine functions. A modification of the Albert- Welton theory of neutron attenuation is used for fast neutron dose rate calcuiations. Combination of buildup factors is used with exponential attenuation to compute gamma ray dose rates. The program requires four magnetic tape units and two frames of magnetic core memory on an IBM 704. Magnetic drum memory is

The steady-state energy distribution is obtained for a group of initially monoenergetic charged particles slowing down in a filly ionized gas. The distribution function is obtained analytically by solving the FokkerPlanck equation in energy space. With reference to thermonuclear reactions, the results obtained suggest that in some situations the contribution of the slowingdown distribution to the reaction rate may be significant. (auth)

The stability of the interface between two immiscible fluids moving at a uniform rate through a porous medium is investigated. The conditions for stability are derived, and the rate of growing of instabilities of specified wavelength is obtained. The expression for the rate of growth of instability is similar in form to that obtained by Taylor for the case of uniformly accelerated incompressible liquids, but the growth rate is fouud to be inversely proportional to the wavelength rather than inversely proportional to the square root of the wavelength. (auth)

Liquidus temperatures in the aluminum -uranium system have been redetermined for alloys containing 13 to 50 wt. % uranium. Thermal analysis, electricalresistance measurements, and metallography were employed in the investigation. The binary aluminumuranium alloys studied and, their corresponding liquidus temperatures are as follows: 17 wt. % uranium, 755 deg C; 17.5 wt. % uranium, 780 deg C; 24.5 wt. % uranium, 954 deg C; 30.9 wt. % uranium, 1068 deg C; 41.6 wt. % uranium, 1190 deg C; 51.2 wt. % uranium, 1265 deg C. Eutectic and peritectic temperatures were determined to be at 640 and 732 deg C, respectively. Binary alloys containing ternary addition of up to 1 wt. % silicon and up to 0.5 wt. % magnesium were studied also. Neither silicon nor magnesium were found to have any effect on the liquidus temperatures. However, silicon lowered the peritectic temperature from 732 to 700 deg C and among alloys coataining less than 30 wt. % uranium had a refining effect on eutectic UAl/sub 4/ particles. The only effect that could be attributed to the magnesium addition was a tendency toward coarsening the UAl/sub 4/ particles in alloys containing less than 30 wt. % uranium. (auth)

Work on circuits for high-speed computers, iterative methods for linear equations, hydrodynamic flow problems, and switching circuit theory are reported. The operation and use of ILLIAC for May are summarized. (For preceding period see AECU-3760.) (T.R.H.)

In order to facilitate reactor design studies a compilation of calculated two-group constants averaged over the infinite-medium flux produced by a fission source was made for approximately 80 materials of interest to reactor engineers. A comparison with available experimental age measurements is included. (auth)