A 500 MWe sodium-cooled, PuO2-UO2 fuel, fast spectrum reactor design is presented, which is calculated to have a fuel cycle cost in the civinity of 1 mill/ekw hr, and to have important safety features due to an appreciably negative Doppler effect.

This document provides the final report on the research project of chemical milling of counterbore recesses in the uranium wall of Zircaloy-2 clad uranium tubes. The scope of work, results and conclusions, and experimental procedures are provided.

A free body diagram of the bellows will show the possibility of three forces -- one in each direction, three moments -- one in each plane, and the internal pressure. Any or all of these forces and moments may fluctuate due to variations in a driving force, e.g., separation of streamlines which creates slugging of flow through an elbow. Whereas the static equilibrium condition can be analyzed and stresses and strains computed, the dynamic condition cannot be approached without information on the magnitude, frequency and location of the exciting force. Having the latter, some evaluation of the stresses to be expected can be made. By combining strains (or stresses) due to the various forces and moments, the point of maximum stress can be located and the point of maximum stress fluctuation for the fatigue cycle-amplitude-range curve can be determined. Further consideration must be given to stress concentrations. With the complete analysis in mind, we must determine how some of these forces and moments effect the tests and delineate what can he expected from the tests. This report considers each force or moment by itself and studies its relationship to the tests.

This report details model studies performed as required by the design, development, and research contract between the General Electric Company and Washington State University. These studies provide analytical considerations for K-Downcomer and Bellows.

During the 0800--1600 shift on July 7, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 3 and Loop 4 instruments indicating a possible fuel element failure in Loop 1. The KE Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant samples and a thermocouple wire sample taken from Loop 1.

An O III N, I and E dingot element exhibited several transverse cracks when it failed in tube 2986 DR. Detailed examination in the Radiometallurgy Laboratory was requested to determine the cause of failure and obtain the ingot number. The element was so badly damaged that it was impossible to determine the exact cause of failure. Reaction between the coolant and fuel occurred at the internal surface around the spire over the total length of the element. Reaction was the greatest near the midpoint where the transverse cracks occurred and was least in the male end. Metallography of both longitudinal and transverse sections revealed that the metal quality of the fuel vas good. Cracks which originated from the oxide extended in both the longitudinal and transverse directions. The fuel near the core, which was insulated by oxide, was annealed but had not been heated into the uranium beta phase. One transverse crack which appeared to have water entry was observed approximately two inches from the male end. The ingot number was UZ 5751 B. After removal of the cladding at the ends, the uranium was bright dip etched and no defects were observed in the surface metal.

Three self support, natural uranium, I & E production fuel elements, which exhibited serious in-reactor cladding corrosion were selected from several tubes of discharged pieces from PT-IP-272-A-FP. The elements were transferred to the Radiometallurgy Laboratory for detailed examination to determine thickness of the remaining cladding and measure any irradiation induced dimensional changes in the fuel cores. Each element had four support tabs attached to each end and was from Parent Lot KT.009. The fuel geometry of all three was C IV NS.

The proposal to reduce P{sub 32} in reactor effluent by increasing aluminum sulphate and bauxite feed to 18 ppm while maintaining 7.0 pH water is estimated to cost $1,368,000. This represents an increase of $507,000 over FY 1962 budgeted cost for aluminum sulphate, bauxite and sulphuric acid. The basis for the cost estimate is provided, and detail calculations are given.

A direct numerical integration of the integral equation for the average collision density in the absorber was previously suggested in a discussion of resonance absorption. The implementation of this program is considered. The method of calculation, comparison with experimental data, and the computer code developed are described. The method of integration, computation of cross sections, selection of mesh size, integration interval, outside correction, the Dancoff correction, and unresolved resonances are discussed. Resonance integrals for U/sup 235/ and Th2/sup >/s3>s/sup 2/ were calculated and compared with experiment. (M.C.G.)

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A total of 455 mlce, rats, gulnea plgs, and rabbits was subjected to lmpact at velocitles ranglng between 25 ft/sec and 51 ft/sec. The deslred velocities were generated by allowlng the anlmals to free-fall from various helghts to a flat concrete pad. The ventral surface of each anlmal was the area of impact. Problt analyses of the 24-hr mortallty data ylelded LD/sub 50/ lmpact veloclties with 95% confldence limits as follows: mouse, 39.4 (37.4 to 42.0) ft/ sec; rat, ft/sec; and rabbit, 31.7 (30.2 to 33.3) ft/sec. The LD/sub 50/ figures for the mouse and rat were slgnificantly higher, statlstically, than those for the gulnea plg and rabblt. The small spread ln the LD/sub 50/ values suggested little variation ln the tolerance of blologlcal systems to impact. Further, the steepness of the mortallty curves lndicated a narrow survlval range to lmpact. Extrapolatlon of the experimental data to the 70 kg anlmal yielded a predicted LD/ sub 50/ impact velocity of 26 ft/sec (18 mph). Literature relevant to the human case was revlewed and the tentative appllcabllity of the predlcted flgures to adult man ls discussed. (auth)

A shearing tool was developed for remotely controlled severing of pipes or structural members. The shear is rotated about its axis in a wrist motion by the pumped hydraulic fluid that also powers the shear blade. It can be used in a stationary mounting or suspended from a crane. A C-shaped support for the shear was designed to pass through a small top opening of a shielded cell. The controls for manipulating the shear pass through or along the Cframe. The shear jaw opens to 5 in. in height and 7 in. in width, and the total weight of the tool is only 575 lb. It was used to cut metal sections 4 3/4 in. thick and 4-in. sched.-40 stainless steel pipe. (auth)

Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)

Flexible Monte Carlo programs FMC-N and FMC-G (GE-ANPD Programs 516 and 515) are digital computer programs which apply Monte Carlo methods to simulate neutron and gamma ray life histories, respectively, in a source-shield configuration. The programs were designed for flexlbility in the geometrical, material, nuclear, and source descriptions of source-shield configurations and variance reduction techniques. The programs were also designed to optimize the use of fast memory and to provide complete freedom in the dimensions of the various input quantities. The programs are coded for an IBM-704 computer with a fast memory capacity of 32,768 storage locations and eight magnetic tape units, and for an IBM7090 computer wlth a fast memory capacity of 32,768 storage locations and ten magnetic tape unlts on two date channels. No magnetic drum storage is necessary for either computer. (auth)

Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)

A mathematical model has been developed for estimati the burnup at which mechanical failure occurs in dispersion fuel elements. It is postulated that failure at low temperature, < 900 deg F, occurs as a result of brittle fracture of an elastic matrix when the intensity of the stress locally reaches the ultimate strength of the material. The contributions of fission gas pressure and thermal stress are incorporated in the stress analysis. Because of the complexity of the stress distribution and the failure process, it was necessary to make stringent assumptions in order to have a workable model. Within the framework of the postulates, burnups to failure are predicted for several values of certain important parameters and compared with burnups to failure obtained from a plastic yield model for failure developed by previous investigation. The two models give good agreement for the special cases considered. Of the parameters examined, relative density of the fuel particles has the greatest influence on predictions of allowable burnup. The thermal stress and volume fraction of fuel play minor roles. (auth)

A method is presented for the determination of uranium (as U/sup 238/) in uraniuni-loaded graphite fuel elenients by a non-destructive, direct radioactivity analysis technique. A 200-cbannel pulse-height analyzer, equipped with a 3 in. x 3 in. NaI(Tl) crystal, is used to measure the Np/sup 239/ radioactivity of the neutron-irradiated samples. The amount of U/sup 238/ in the test samples is deterimined quantitatively by comparing the Np/sup 239/ radioactivity induced in each sample with the Np/sup 239/ radioactivity induced into known standards of U/sup 238/ processed under the same conditions as the test samples. The limit of detection for U/sup 238/in samples of normal uranium composition for this method is about 1.0 x l0-4 ug. (auth)

Structural evaluations of the upper head of the EGCR pressure vessel were made. The configuration throughout the cluster region in the vessel was found to be structurally adequate. The primary and primary-plus-secondary stress intensities for the burst-slug detection and gas outlet nozzles were found to be within the allowable limits. However, the complete design evaluations of these units cannot be made until the temperature distributions are known. (auth)

In previous letters the authors have reported a {Sigma}{pi} resonance observed through the study of the interaction of 1.15-Bev/c K{sup -} meons in hydrogen in the Lawrence Radiation Laboratory 15-in. bubble chamber. They now wish to report the results of the study of the three reactions: (1) K{sup -} + p {yields} {Sigma}{sup +} + {pi}{sup -} + {pi}{sup -} + {pi}{sup +}; (2) K{sup -} + p {yields} {Sigma}{sup -} + {pi}{sup +} + {pi}{sup +} + {pi}{sup -}; and (3) K{sup -} + p {yields} {Sigma}{sup 0} + {pi}{sup 0} + {pi}{sup +} + {pi}{sup -}. Although reactions (1) and (2) are readily identified and measured, reaction (3) cannot be identified unambiguously. Accordingly, they discuss first the results pertaining to reactions (1) and (2). Nineteen events of type (1) and 13 events of type (2) were observed, corresponding to cross sections of 0.19 {+-} .06 and 0.12 {+-} .05 mb, respectively. In a search for possible {Sigma}{pi} resonances, they have plotted in Figure 1 histograms of the invariant masses of the {Sigma} and each of the three pions in reactions (1) and (2). Figure 1b refers to the {Sigma} and pion of like charge; Figure 1a to the …

A survey and re-evaluation of previous work on polyurethane and polyurethane--epoxy copolymer systems was initiated to determine which phases are more productive than others. The effects of varying excess polyol content were studied. Work was carried out to define the amounts of butamediol that the system Adiprene L-213-ferric acetyl acetonate can tolerate and still be thoroughly cured. An experimental diallyl phthalate formulation was made and tested. A survey is being made of potential sources of kilogram quantities of Th/ sup 2//sup 3//sup 0/ in the United States. Analyses of various samples indicated concentrations almost three times as great as previously reported. The half-life of Rain was recalculated to include new data, and the results are reported as a function of the resolution time of the gas flow proportional counter. A method is being developed for determining the coincidence correction in porportional alpha counters by following the decay of a short-lived isotope. Additional determinations were made on the density of liquid cerium by the vacuum pycnometer method using tantalum pycnometers of about 0.5 cm/sup 3/ capacity. The viscosity of molten plutonium metal was investigated from 648 to 950 deg C with a cup viscometer. The construction of the hightemperature colorimeter was …

Generalized computer codes were devised for solving stress problems of some complexity. These codes were applied to stress problsms relating to the graphite moderator elements in the Experimental Gas-cooled Reactor. The stress relief obtained by aubdividing the moderator elements was evaluated. The distontion and bending moments of the elements were also determined. (auth)

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