From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."

Abstract: This report gives a general description of the single stage axial compressor blade test facility located at the Oak Ridge Gaseous Diffusion Plant, Oak Ridge, Tennessee.

From introduction: This report presents the summary of results, reference plant design, cost analysis, and research and development program for a liquid metal fast breeder reactor.

Abstract: The results of three separate inpile capsule experiments are presented.

Introduction: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. The counting mode of operation will be used at low neutron flux levels and the RMS voltage fluctuation mode (Campbell Theorem) will be used at high neutron flux levels. The June-September Progress Report (GEAP-4386) shows how the RMS voltage mode can be used, discusses counting problems with long cable and ways of maximizing signal levels. This report discusses primarily the effect of gamma on counting with in-core ion chambers and the range of neutron flux measurable in the RMS voltage mode. Readers are referred to GEAP-4386 for a summary of all previous progress to attain the objective of PA-22.

Summary: Heat transfer tests employing the two-rod test section without film tripping devices have been completed. Representations defining critical heat flux, transition boiling and film boiling behavior at high pressures and over a steam quality range of 25 to 90 percent are shown. Fabrication of a new observational test section was completed and initial test results with high-speed motion pictures were obtained. A test loop instability which was found to affect transition boiling behavior was detected and partially eliminated.

Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, fuel testing in TREAT, fuel performance evaluation, fast-flux irradiation of fuel, and reactor dynamics and design.

Abstract: A potentiometric study of the complex formation between citric acid (H3L) and the uranyl ion at 25° and ionic strengths of 0.1 and 1.0 (KNO3) is reported From the concentration dependence of the formation constant, it is concluded that polynuclear complexes are formed in which bridging between metal ions occurs through carboxylate and hyroxyl groups of the ligand. The values of the logarithms of the formation constant of the metal checlate [UO2L-]/[UO2+][L3-] and of the dimerization constant [(UO2)xL22-]/[UO2+][L3-] are found to be 7.40 and 4.07 respectively. Infrared absorption measurements of protonated and dissociated carboxyl groups in aqueous uranyl citrte system indicated the presence of both carobxy-late and hydroxide bridging in the polynuclear complex. On the basis of the "core plus links" treatment of polynuclear complexes, the polymeric species in solution in the buffer region between 3 and 4 2/3 moles of base per mole of metal complex appears to be predominantly (U)2)2L2((OH)5(UO2)2L2)216-.

Report issued by the University of California Lawrence Radiation Laboratory discussing a method of updating library circulation records on an IBM 1401 computer. The report describes the methods of generating and updating the records using transaction cards to create computer tapes that are sorted and updated to prepare current reports of circulation information.

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Forty-six fuel pellet faces have been auto-radiographed. These faces have been prepared from twenty-three pellets by making an exposure before and after the removal of an additional ten mils of fuel. A substantial number of large "hot spots" continue to appear. The largest spot so far observed was 44 mils long, 20 mils wide, and of the order of 20 mils thick. This spot has a PuO2 concentration which varied from 70% on the periphery to 100% at then center. There is some evidence that the segregated regions are elongated with their long axes perpendicular to the direction of the pressing of the green pellet. Determination of the size and concentration distribution is continuing. The EPITHERMOS code now seems to be operating correctly. A test problem for a typical water lattice converged in eleven iterations. The computation of the spectrum for a pure water medium gave results which agreed very well with the expected 1/E spectrum. At the end of the quarter, the program fuel element …

Summary: All experimental work under the Corrosion Mechanism task has been completed. The remaining topical reports are being prepared by D. L. Douglass, now on assignment at Mol. Experimental work on the first round of 31 alloys and on the second round of 10 alloys has been completed. Steam exposures of at least 3000 hours were finished for all the alloys at all test temperatures, with exposures of some coupons to 6700 hours. Mathematical expression have been derived to describe all first round data for corrosion rates and hydriding rates at 300, 400, and 500 degrees C as a function of Nb, Cr, Fe, and Cu content. Solution of the equations for particular service temperatures yield Zr-Cr alloys at optimum at lower temperatures and Zr-Cu-Fe alloys as optimum at the higher temperatures. The second round test results show that neither Ni nor Be additions to Zr-Cr or Zr-Cu improve the performance over that of the optimum Zr-Cr or Zr-Cu-Fe alloys. For the first round heat treatment used, post-corrosion ductility depends on two factors in addition to alloy composition and hydrogen content: crystallographic texture and intermetallic aging reactions. Alloys with a high original ductility are embrittled less by a given amount …

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

From abstract: "A detailed description of a reference 1000-MWe fast breeder reactor plant is presented, together with design specifications and the experimental bases for the design."

From introduction: "Documentation of the various considerations and design techniques involved in the design of the reference 1000-MWe fast oxide breeder reactor."

"Designers, builders and operators of water cooled reactor systems have been queried regarding the range of parameters which should be investigated in a study of piping rupture."

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.

From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."

Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.

From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."

The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.

Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development. All fuel irradiation has been terminated with the final shutdown of the VBWR. The high burnup average achieved by a single assembly in the group is 10,000 MWD/T (assembly 1F). Twenty-one of the original 24 assemblies have failed or are suspected of failure. Profilometer tests rung on HPD assembly 2E, Rod B, indicate that localized clad deformation occurs during operation. (2) Task 1B-Fuel Fabrication Development. Assembly. All fuel irradiation has been terminated with the final shutdown of the VBWR. The highest average burnup achieved by a single assembly in the group was assembly 4S with 8400 MWD/T. All assemblies in the group have failed or are suspected of failure. The Phase I developmental fuel continues to be irradiated in the Big rock Point reactor with the lead assembly having reached 1500 MWD/T. Fifteen phase II developmental assemblies are being construction for insertion at Big Rock Point in March. Engineering is underway to provide one instrumented assembly probe and two spare flowmeters for …