The GCRE-I hazard summary report is supplemented in the following areas: geometry and operation of the steam cooling system, the reactor coolant by-pass, and by-pass valving; the means by which by-passed circuits are prevented from remaining unintentionally disabled; design details, and details of procedure for core flooding operations. (A.C.)

The performance, reliability, stability, and reactivity lifetime variations of the Shippingport PWR are determined under normal steady state conditions. These characteristics are studied over a period of 758 EFPH, at a power level of about 60 Mw(e). Flux-tilt corrections and plant operations during this time are described. (T.F.H.)

Photograph taken for a story in the Daily Oklahoman newspaper.

Photograph taken for a story in the Daily Oklahoman newspaper.

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Daily newspaper from Sapulpa, Oklahoma that includes local, state, and national news along with advertising.

Monthly newsletter from Dallas, Texas published by the Stamps Quartet Music Company that includes news and information concerning gospel music along with advertising.

Data are summarized from a series of recently published papers which indicate that the tissue iron enzymes as well as the blood hemoglobin level play a role in the iron-deficiency state. Results from a study of the derivation, roles and fate of the antibody-forming cell in the rat indicate that antibody- forming cells in lymph nodes may be released to circulate in the efferent lymph and peripheral blood. Evidence indicates that the circulating cells may still contain formed antibody. Because of thcir form these circulating elements are designated lymphocytes. Strong evidence also implicates the plasma cell in the immune phenomenon. It appears that thc circulating blood contains two small round cells, one produced in the germinal centers of the spleen and other lymphatic tissue and having no known relationship to antibody production, while the other is apparently produced in the splenic red pulp, contains antibody, and is related intimately to antibody synthesis. In terms of site of production and function the two cells appear unrelated. Papers included which have been accepted for publication cover the effect of concurrent feeding of Tween 80 on the carcinogenicity of orally-administered 3-methylcholanthrene, data on the long- term survival of irrailiated mice treated with homologous …

Two designs of adiabatic calorimeterss in which the surroundings follow the temperature of a test specimen at all times from the lowest temperature achieved by cooling up to room temperatures are described. Values for the heat capacity of oxygen-free, high conductivity copper are given in order to show the reliability to be expected from determinations of heat capacity of elements in which the self-heating by radioactive disintegration is appreciable and can be used as the sole source of heating. Equations based on least-squares analysis of data are listed for the OFHC copper. The methods of numerical integration used for thermodynamic properties are described and values of entropy and enthalpy of copper at 298.15 deg K are shown. (auth)

A summary of work on the problems of reprocessing Enrico Fermi Fast Breeder Reactor between July 1958 and January 1959 is given. Dissolution experience with the Zr-clad U-Mo fuel pins is related. Corrosion of the stainless steel waste evaporator was studied. Nuclear hazards, flow sheet design and chemistry, and waste handling studies are also reported. (For preceding period see BNL-511.) (T.R.H.)

The lectures were developed at the International School of Science and Engineering at Argonne National Laboratory for the Argonne employees but are considered adequate for a one-semester-hour course. Reactor shield design and associated shielding problems are discussed as well as problems associated with radioactivity of coolants and components, radiation heating of structural materials, and handling of spent fuels. (A.C.)

APPR-type dispersion fuel element specimens containing temperature to respective burnups of approximately 50, 20, and 20% of uranium with no evidence of gross dimensional changes or loss of structural integrity. Blistering and/or core cracking has occurred when sections of 17.9 wt.% UO/sub 2/ specimens irradiated to burnups over 40% of uranium were subjected to post-irradiation annealing at 600 deg F for 24 hours. Post-irradiation core hardness measurements indicate that significant differences in irradiation damage exist between the various specimen types. These data indicate that the effects of the fabrication variables investigated in this program are as follows: The severity of irradiation damage in dispersion type fuel elements is inversely proportional to the UO/sub 2/ particle size of the fabricated plate. The particle size of the UO/ sub 2/ powder used in preparation of the initial core compact and the method of preparation of the UO/sub 2/ powders largely determine the final UO/sub 2/ particle size of roll-bonded, dispersion fuel plates. The particle size of the stainless steel powder used in the initial core mixture and the degree of cold reduction during final sizing of the fuel plate are apparently of relatively minor importance, at least for the systems investigated in …

A method of obtaining the few-group form of the P/sub L/ and double-P/ sub L/ equations is given for slab geometry. Anisotropic scattering is allowed within specified limitations. The difference equations and associated recursion relations are discussed; the features and restrictions of FLIP are explained; and a detailed discussion of the input and output is presented. Operating intructions are given, and a sample problem is included. (auth)

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Caption: "Three students from the Oklahoma School of Science and Mathematics greet Dr. David Suzuki, center, as the Canadian geneticist, author and PBS-TV star arrives at Will Rogers World Airport on Wednesday."

Physics experinments were performed on the SM-1 (formerly APPR-1) core to evaluate temperature and pressure coefficients, transient xenon, neutron source requirements, safety margin, and core reactivity as a function of core life. The temperature coefficient was measured as --3.5 plus or minus 0.13 cents/ deg F at 443 deg F several times throughout life and no change with life time is thus far indicated. The hot to cold reactivity change (440 to 70 deg F) was 6.70 dollars. The pressure coefficient was 1.05 plus or minus 0.05 cents per 100 psi at 115 deg F. Reactivity value for equilibrium xenon was found to be 3.32 dollars and peak xenon reactivity was 4.64 dollars. The 15 curie Po Be source and the beryllium photoneutron source have proved adequate for safe stantup. The safety margin 80% rod insertion'' was found to depend strongly upon the rod configuration. The core reactivity has decreased approximately 5.8 dollars up to 9.1 Mwyr leaving an estimated 5.6 dollars to be used. The core life is expected to be 15 Mwyr. All measurements indicated satisfactory performance of the (SM-1) core. (auth)

Estimates were made of the amount of neutron poisoning, in the form of boron rods, required to maintain suberiticality in a tank used for dissolution of solid fuel elements. The tank under consideration was a cylinder 19.5 inches in diameter and 6 ft in height. Maximum concertrations of fuel and fertile material resulting from dissolution of various type fuel elements sre tabulated. Below the maximum concentrations listed, it was found that the limiting poisoning requirements are associated with dissolution of the NS Savannah elements. About five 1-inch diameter rods appear necessary: a centrally located rod and four rods in a square array each about 5 inches from the central rod. (auth)

Experimental extrusions were prepared from mixtures of atomized aluminum alloy and several powdered additives, including SiO/sub 2/, AlPO/sub 4/, and Al/ sub 2/O/sub 3/. Some of the extrusions failed during corrosion testing in water at 290 and 350 C. Others corroded in approximately the same fashion as wrought X8001 alloy. The ultimate tensile strengths of these extrusions at 316 C were approximately two and one-half times greater than that of wrought X8001 alloy. (auth)

In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. ( A.C.)

A preliminary study has been made of an impregnated graphite reactor to produce helium at 2400 F for process heat uses. The proposed facility will determine the characteristics and problems associated with operation of unclad graphite fuel. Volatile fission products will escape from the fuel elements into the helium stream, which will be continuously purified. Laboratory studies have shown that impregnated graphite will perform satisfactorily at the proposed conditions, and a simple fuel cycle has been developed. (auth)

The HRT chemical plant hydroclone loop was operated for 829 hr during reactor run 17 and removed 709 g of corrosion product solids from the reactor fuel stream, The composition of corrosion product solids removed averaged 49% Zr, 22% Fe, and 4% Cr, markedly different from solids removed during run 16 which anaremoved by the chemical plant was equivalent to approximately 19% of the stainless steel and 2.5% of the Zr core corrosion products produced in the reactor during run 17. U removed as a solid phase during this run totaled 200 g. Fission products concentrated by the hydroclone included Ru, Zr, Te, Mo, Ce, Y, and Nd. Less than 2% of the I produced by the reactor was found circulating in the reactor fuel, and there was no condence indicated I is held up approximately one day in the high-pressure system compared with a theoretical down rate. (auth)

Theoretical conditions were investigated for determining the thermal deflection of the definitive design unshrouded Yankee fuel assembly and the compromise design fuel assembly. In addition, an experimental study was completed on the thermal deflection of the compromise design fuel assembly from linear and nonlinear temperature gradients. All of the theoretical analyses performed on the definitive design clearly indicate that excessive bowing in the order of 0.150 inch may occur within the reactor during normal operation. Slnce the nominal clearance available in this design between a fuel assembly and an adjacent control rod is about 0.120 inch, interference between a fuel assembly and its adjacent control rod can occur, resulting in restricting the movement of the control rod. When buildup of mechanical tolerances are considered, this condition becomes more severe. Redesign of the definitive design fuel assembly thus became mandatory to prevent interference with the movement of control rods. The compromise fuel assembly design evolved as a result of these considerations. The compromise design employs the use of the brazed ferrule fuel sub-assembly design concept, but incorporates several fundamental changes in design that increase clearances adjacent to the control rod to reduce thermal bowing of the complete assembly. The compromise fuel …