The chemical feasibility of the direct, continuous reduction of UF/sub 6/ to U with Na was shown in several tests. Up to 93.5% of the U content of UF/sub 6/ continuously reduced by Na in a reaction vessel was recovered as massive U metal of acceptable purity. A semicontinuous reactor for continuous reduction is described. (D.L.C.)

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 performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GGBR), and deuterium- moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site. The maximum annual fuel yields were 1.5 mills/ kwhr. The minimum estimated fuel cycle costs were 0.9, 0.6, 1.0, 1.2, and 1.3 mills/kwhr at fuel yields of were 0.9, 0.9, 1.5, 1.5, and 1.3 mills/kwhr. Only the AHBR and the MSBR are capable of achieving fuel yields substantially in excess of 4%/yr, and therefore, in view of the uncertainties in nuclear data and efficiencies of processing methods, only these two can be listed with confidence as being able to satisfy the main criterion of the AEC longrange thorium breeder program, viz. a doubling time of 25 years or less. The development effort required to bring the various concepts to the stage where a prototype station could be designed was estimated to be least for the AHBR, somewhat more for the MSBR, and several times as much for the other systems. The AHBR was judged to rank first in …

The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium- moderated gascooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected with continuous processing of fuel and fertile streams. The maximum annual fuel yields were 16, 7, 4, 4, and 4.5%/yr, respectively at a fuel cycle cost of 1.5 mills/kwhr. The minimum estimated fuel cycle costs were 0.9, 0.6, 1.0, 1.2, and 1.3 mills/kwhr at fuel yields of 7, 1, 1, 2, and 3%/yr. At a fuel yield of 4%/yr, the costs were 0.9, 0.9, 1.5, 1.5, and 1.3 mills/kwhr. Only the AHBR and the MSBR are capable of achieving fuel yields substantially in excess of 4%/yr, and therefore only these two can be listed with confidence as being able to satisfy the mdin criterion of the AEC long-range thorium breeder program i.e., a doubling time of 25 years or less. The development effort required to bring the various concepts to the stage where a prototype station could be designed was estimated to be least for the AHBR, somewhat more for the MSBR, and several times as much for …

Design and construction specifications to be followed in the development of the reactor, its associated systems and experimental facilities, and the housing and required services for the facility are presented. The testing procedures to be used are outlined. (D.C.W.)

Heavy-ion reactions in the low-Z region were investigated with 27-Mev nitrogen ions from the 73-inch Cyclotron and with 30-Mev oxygen ions from the Tandem Van de Graaff. Experiments included studies of angular distributions and excitation functions for transfer reactions, compound-nucleus reactions, effects of angular momentum on the density of nuclear states, and so-called Ericson fluctuations in the compound nucleus Si/sup 28/. Nuclear reactions induced with 22-Mev protons in the 86-Inch Cyclotron were used in studies of the pickup- reaction mechanism, shell-model studies from pickup reactions, scattering and the optical model, and level schemes in highly deformed nuclei. In theoretical investigations of the mechanisms of nuclear reactions and related nuclear- structure information, the elastic scattering of complex particles was analyzed via the optical model; the applicability of the distorted-wave method to stripping reactions was investigated, and the inelastic scattering of carbon ions from carbon was examined. Experimental studies with the eightsector electron model, Analogue II, led to very successful deflection of the beam in November 1962, a significant advance in accelerator technology, This investigation, still incomplete, eases one of the major uncertainties associated with the proposed Mc/ sup 2/ cyclotron. The radioactivity resulting from the residual undeflected beam being dumped onto …

This document lists the physics factors for the K Reactors following the transition to the KV fuel element geometry and zirconium tubes. Each new parameter with the zirconium tube lattice has been calculated relative to the factors used with aluminum tubes and the KIV fuel elements. The purpose of this document is to provide working values for plant assistance use during the transition to the zirconium lattice. In some cases, where there are large uncertainties in the absolute values, the conservative end of the range has been provided for present operational use in safety and control administration. Refinement and publication of ``best`` values for the zirconium lattice based on the extensive experimental and calculational studies are included in future Reactor Physics Unit programs.

Centrifugally cast stainless steel piping was selected for the primary piping of Spert III, a 2500-psi, 650 deg F water moderated and cooled nuclear reactor system, because of the significant cost advantage of using cast piping and because of favorable results from metallurgical examinations of the material. Essentially no operating experience was available at that time on the performance of cast piping in elevated pressure and temperature service. Presented are a brief history of operational experience with this piping in Spert III, the results of a recent plant inspection, and the results of the initial metallurgical examination of centrifugally cast material. On the basis of the Spert experience, it can be concluded that centrifugally cast stainless steel pipe has given adequate service under cyclic operation and probably is equal to high-pressure stainless steel piping fabricated by other methods. However, due to the limited general use of this material, no statement can be made as to the usual commercial quality of cast piping or to its performance under conditions other than those reported. (auth)

None

None

None

The production reactors operated by Douglas United Nuclear, Inc., use treated Columbia River water as the coolant on a once through basis. Thus, radionuclides formed largely by the neutron activation of river salts are discharged to the river. One method of reducing the quality of radionuclides in the effluent is to increase the efficiency of parent isotope removal during the water treatment process. Prior to 1961 the water treatment process for preparing reactor coolant had been improved to the point that reactor quality coolant could be produced using an average alum flocculent feed rate of 6 ppM. Laboratory experiments carried out in 1959 and 1960 demonstrated that a markedly increased removal of parent isotopes resulted when alum feed rates in the neighborhood of 20 ppM were used. The results were confirmed by two half-plant tests of short duration in July, 1961, all water treatment plants began to use alum at a somewhat arbitrarily selected rate of 18 ppm. The practice Continues to date at all plants except at the K Reactors. The K Reactor alum feed has been limited to a nominal 15 ppM because of the high filtered water requirements. The use of the high alum feed rate did …