The flowsheet visualized from development work thus far for final plutonium recovery and purification will accept as feed a Purex partition stream without feed adjustment beyond the usual reoxidation. Extraction with trilaurylamine at approximately 0.3M appears suitable for 20 to 60 g Pu/liter product from 0.5 to 2 g Pu/liter feed. Scrubbing with either ((2 M or))2 M HNO/ sub 3/ is possible. Acetic acid is at present the first choice for stripping agent, with oil-soluble and aqueous-soluble organic reductants as alternates. (auth)

The activation energy, activation volume, snd frequency factor were evaluated for yielding (delay time for yielding, upper yield stress, lower yield stress, and Luders band propagation) and flow (friction stress, flow stress, and dislocation mobility) for various irons and steels from data in the literature. It was found that the values of these flow parameters and their stress dependence were the same, within experimental error, for both yielding and flow, and for all the materials considered. This suggests that either the same dislocation mechanism is controlling in every case, or that one or more mechanisms possees approximately the same values for these parameters. The dislocation mechanism for which there was closest agreement between theoretical calculations snd experimental data was overcoming the Peierls stress. On the basis of the available experimental data and the present analysis, it is suggested that the upper and lower yield stresses in iron and steel may represent the sudden generation of a large number of dislocations by the double cross-slip mechanism of Koehler and Orowan, rather than the breaking away from a Cottrell atmosphere. (auth)

"The present work describes some computer-oriented techniques for the application of the laws of quantum mechanics to the problems of determining basic structure of diatomic molecules. At times, calculations of the type described here yield results which can be compared directly with experiment to check the validity of the hypotheses and technique used they may predict the results of unobserved experimental phenomena; and, in many instances, they provide quantities which are necessary for the interpretation of experimental data but which cannot be directly measured."

Report giving tables of the linear contraction relative to 293 ºK, (L293ºLT)/L293, and the linear expansion coefficient, dL/L293dT, of thirty elements, forty-five alloys, twenty-two other inorganic substances and twenty plastics and elastomers in the temperature range, 0 to 300 ºK.

The distortion behavior of graphite as a function of irradiation temperature is reviewed. The behavior of needlecoke and CSF graphite was examined over moderate exposures in the GETR. Results showed needle-coke to be less contracting than CSF. Details of contraction show a minimum contraction rate per 10/sup 21/ nvt at 600 to 800 deg C for both types. Limitations to be placed on the data presented are listed. (P. C.H.)

The solubilities of uranyl dlbutyl phosphate, uranyl monobutyl phosphate, ferric dibutyl phosphate, and ferric monobutyl phosphate were measured in aqueous nitric acid solutions ranging from 0 to 3 M and in 30% TBP in Amsco 125-82 solution containing 0--0.7 M HNO/sub 3/. For the respective compounds in the aqueous phases, as the acidity increased from 0 to 3 M, the solubilities increased from 0.004 to 0.7 g U/liter, O.O5to 50 g U/liter, <1 to 30 mg Fe(III)/ liter, and 0.003 to 3 g Fe(III)/liter; corresponding solubilities in the organic phases increased with acidity from 14 to 165 g U/liter, 11 to 110 g U/liter, <O.5to 4 mg Fe(III)/liter, and <0.002 to 1.5 g Fe(III)/liter. All these compounds foamed or formed very flocculent solids in the aqueous phases snd tended to settle slowly in the organic phases and rise to the surface in the aqueous phases, suggesting that they would be interface seekers in two-phase aqueousorganic systems. (auth)

During the 1600--2400 shift on August 7, 1960, the delayed neutron monitor on KER Loop 2 indicated a high coolant activity level. Sympathetic responses were also observed on the Loop 1, 3 and 4 monitors. This indicated a possible fuel element failure in Loop 2 and the KE Reactor began shutdown operations immediately. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant and coupon samples taken from Loop 2 after shutdown.

A colorimetric method was developed for the determination of uranium(IV) in the presence of uranium(VI), nitric acid, hydroxylamine sulfate, and hydrazine. A coefficient of variation of 2.4% (n = 25) was obtained. (auth)

The results of a critical-experiment program conducted to study the Hallam Nuclear Power Facility (HNPF) reactor concept and to verify design parameters are presented. Experimental procedures and results are given, and comparisons are made with calculational techniques currently in use for determining the nuclear characteristics of the HNPF reactor. (auth)

ABS>The preparation of germanium hydrides, by the dropwise addition of al alkaline solution of hydroborate and germanate to aqueous acid, was studied systematically. As much as 70% of the germanium in solution could be converted to germane, Digermane, trigermane, and a polymeric germane were also obtained, and the infrared absorption spectra of gaseous trigermane and of polymeric germane were recorded. (auth)

Graphical presentation of K-factors for eight isotherms, published data on the solid-vapor region, and a bibliography of approximately 450 references.

tems were cast and cured. Results of chemical tests on aa epoxy curlang exudate are included. Comparison of solvent effects on retention of radioelements by stainless steel was started and data are tabulated for Ac/sup 227/, Th/sup 227/, a nd Ra/sup 22//sub 3/. Work on protactinium was resumed after suspension of this project in 1960. Methods for preparation of small quantities of highly enriched U isotopes are being examined. Included in the survey are chemical exchange, electromagnetic separation, gaseous and liquid thermal diffusion, gas centrifugation, and photochemical techniques. Continued investigation of viscosities of La and Pr for use in Pu alcontinued along with studies of Pu bearing glass fibers. (J.R.D.)

The variation in concentration of settled beds of flocculated aqueous suspensions of thoria was studied experimentally as a function of the calcination temperature and particle size of the thoria, the temperature and initial concentration of the suspension, and the concentration of added chromic acid. Values of the ultimate settled-bed concentration were obtained by several methods. Dilatant-plastic behavior of one suspension was considered responsible for the formation, in long vertical tubes, of intractable plugs. (auth)

The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.

Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase of the work, a conceptual design study of a 330-Mw (e) central station, was initiated November 1, and is the subject of this report.

A program is described which is devoted to heat transfer and pressure drop measurements on single tube sections with coolant flow only on the inside. The tests were conducted on simulated PM-1 fuel elements. Data are included and data reduction methods are discussed. (J.R.D.)

The original test authorized the discharge of three columns of irradiated fuel elements from KE Reactor as a first step in an Operational Recharging program. Purpose of this supplement is to authorize discharge of any number of columns of irradiated fuel elements after shutdown, and to continue in force Supplement A, with changed timing of operational discharge.

None

The Livermore 90 deg inch variable-energy cyclotron was used to measure the 90 deg excitation function for the Al/sup 27/(p, gamma )Si/sup 28/ reaction. Proton energies between 5 and 13 Mev were used which gave excitation energies in Si/sup 28/ corresponding to the region of the photonuclear giant resonance. Two gamma rays were observed: gamma /sub O/, the groundstate gamma ray and gamma / sub 1/ resulting from deexcitation through the first excited state of Si/sup 28/ at 1.78 Mev. They were detected by a 5-in.-diam by 6-in.-long NaI(Tl) crystal. A Pb collimator was used to improve the resolution of the detector. The results indicated that both gamma /sub O/ and gamma /sub 1/ display the giant resonance behavior; the gamma /sub O/ carve reached a peak value of approximately -8 mu barns/sr at E/sub p/ = 8.75 Mev, while the gamma /sub 1/ peak was approximately -14 mu barns/sr at E/sub p/ = 10 Mev. Both curves displayed the fine structure previously reported by Gove et al. A detailed balance calculation was made, using the gamma /sub O/ data. A comparison with the measurements of Johansson on the total yield of protons from the Si/sup 28/( gamma ,p)Al reaction …

The effect of the many parameters which may influence the failure behavior of coextruded fuel material are being evaluated by Reactor & Fuels Research & Development Operation. This knowledge will be helpful in the design, fabrication, and operation of fuel elements so that the hazards and time involved at failure may be minimized. Many of the various tests performed on unirradiated coextruded fuel material have been in isothermal systems. The tests reported here were performed on power generating coextruded fuel rods. One of the purposes of these tests was to assess the effect of simulated in-reactor power generation and associated thermal gradients and thermal stresses on the defect-test behavior. Another purpose of these tests was to determine the degree of damage that might result to fuel components as a result of interaction (e.g., touching produced by warping or distortion of a failing rod) while at operating powers.

A description is given of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar statibns north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, naturalcirculation boiling water reactor, ccoled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading. The "packaged" concept is incorporated for the initial erection. The plant is not designed for relocation. The design criteria for the prototype necessitate special features. The fuel plates are clad with an alurninurn-nickel alloy (X8001). …

This document consists of information about the cooling systems of Hanford Production Reactors. It is the purpose of this letter, written May 8, 1961, to update recommendations of high-tank temperatures required to insure acceptable high-tank backup support. It does not appear practicable to relate the somewhat arbitrary standards of reference for backup support to process operating limits, i.e., reactor power levels, particularly as a mandatory requirement. For this reason, we have chosen at this time not to include these limits as a process standards` requirement. Considerable emphasis should be placed on insuring that the high-tank backup support be maintained in the maximum practical manner. Tables are attached showing high-tank temperature versus reactor power level relationships to satisfy the intent of our backup criteria and, through compliance, will insure that high-tank flow rates will be adequate during a reactor emergency following the loss of electrical power and steam.

From Abstract: "This Monograph contains a consistent set of tables of thermodynamic properties of a large number of diatomic hydrides, deuterides, and tritides, for the ideal gas state at one atmosphere pressure. In addition to the thermodynamic properties of the molecular gases, the tables also include thermodynamic properties for chemical reactions involving the isotopic exchange of hydrogen."

Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over-all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading." (p. 15)