Programming a computer that optimizes the beam in the Brookhaven AGS is discussed. Layout, method, and routines are given particular attention, and representative data cards are shown. (D.C.W.)

Description of a computer program which optimizes the locations and strengths of magnets for experimental beams at the Brookhaven AGS written for the IBM 7090 computer. Layout, method, and routines are given particular attention, and representative data cards are shown.

The monthly report for the Hanford Laboratories Operation, November 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and technical administration operation are discussed.

This document details the activities of the Irradiation Processing Department during the month of November 1961.

This report attempts in detailing the History, Organization, Principles, and Activities of the John Birch Society.

Tests are performed on Pathfinder superheat fuel element mockups, under reactor conditions of 600 psig, in order to determine the parameters influencing heat transfer from the fuel elements to the moderating water under shutdown conditions. The peak temperatures reached by the superheat elements are also found as functions of the heat generation rate. A mathematical model of the heat transfer system is developed. (T.F.H.)

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Proper method for assessing value of shares of bank stock for ad valorem tax purposes in view of Attorney General Opinions Nos. V-315 and WW-439.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Traveling expenses of the Special House Committee on Escheat Laws.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the removal of a portion of a non-load bearing wall for the purpose of installing a door and appropriate hardware from which the use and benefit would be an improvement in communications and efficiency of the offices in question is prohibited by Section 39 of Article V, Senate Bill 1, 57th Legislature and related question.

The percentage of helium which will bypass the core if the reflector system shown is used is predicted. It is estimated that nominally about 0.1 to 0.2% of the total flow will bypass the core, which is not considered excessive. The most difficult parameter to determine was Z, the gap between the sealing surfaces. The method used to predict Z is presented. The effect of bowing due to a temperature gradient across the seals is discussed. (auth)

A conceptual design and economic evaluation of 300 and 40 MW/.sub e/ steam-cooled fast breeder reactor power plants were performed. A reactor core composed of U-Pu oxide rod-type fuel elements clad with Inconel-X and surrounded by a blanket of depleted UO/sub 2/ fuel was studied in some detail. Reactor breeding ratios of from 1.27 to 1.5 and overall system doubling times of from 20 to 30 years are achievable. For the near term (1967) 300 MW/sub e/ plant, an energy cost of 7.6 mills/kwh is estimated, based on AEC ground rules for privately financed plants and utilities. This cost may go down to 5.7 mills/kwh by 1975. For the 40 MW/sub e/ plant corresponding energy costs are 19.5 and 13.7 mills/kwh, r -spectively. The R&D program required for this reactor concept is estimated at million with an additional million for improvements leading to the 1975 reactor. Investigation of the operational and safety aspects of the reactor indicated that satisfactory procedures can be used for startup, shutdown, and emergency cooling of the reactor. An increase in reactivity upon flooding can be prevented by incorprating small amounts of high resonance absorption material in the core. Preliminary calculations indicate a substantial increase in …

From abstract: This report describes a conceptual design and economic evaluation of 300 and 40 MWe steam-cooled fast breeder reactor power plants performed by NDA under contract with the AEC.

Studies carried out on corrosion associated with the hydrofluorination- dissolution phase in the fused-salt Fluoride Volatility Process are summarized. Corrosion for hydrofluorination-dissolver vessels used in bench-scale and semiworks-scale process development at ORNL is discussed. The results of a study on construction materials for the dissolution phase are presented. Corrosion studies at ANL are described for comparison purposes. A full-size hydrofluorinator dissolver is described. (M.C.G.)

Under the influence of radiation, the coolant-moderator in an organic moderated reactor slowly decomposes to form high molecular weight polymers (high boilers) and a mixture of gases and light hydrocarbons as waste products. Work carried out on the improvement and subsequent operation of a prototype waste- polymer combustion process is described. Operation of the improved unit employing a vortex'' burner confirmed the feasibility of combustion as a disposal method. It was determined that fuel temperatures of 400 deg F and combustion air temperatures of 300 deg F were required for successful operation. The quantity of ash resulting from the combustion was established to be less than 0.5 wt% of the original polymer. It was determined that the efficiency of the primary dust collector varied from approximately 90 to 99%, and that there was no detectable particulate matter in the gas leaving the absolute filter. Attempted activity-balance calculations proved unsuccessful due to extreme difficulties in measurement of the low-level activty of the stack gas. In an effort to further improve and simplify the process system, preliminary evaluation of another burner was carried out. A cost estimate of the combustion process using the Vortex'' burner was prepared, based on data obtained from …

This is the monthly report for the Hanford Laboratories Operation October 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

A dissolver design was demonstrated on a laboratory scale for the electrolytic dissolution of nuclear fuels. Simplified electrodes are used which need not touch the fuel pieces, thus avoiding the usual problems of achieving adequate electrical contact between the fuel and the anode basket. Because a series of electrolytic cells are formed along the length of the dissolver, current efficiency is enormously increased; this technique allows for the use of higher voltage and much lower current than is presently considered essential in plant-scale electrolytic dissolution. (auth)

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Changes in neutron multiplication caused by voids in the island of the HFlR were calculated and measured experimentally. The results indicated that with only water initially in the island the maximum change in neutron multiplication ( DELTA k/sub max) associated with island voids is 0.032 with a corresponding void fraction of 70%. With a simulated 300 g Pu target in the island DELTA k/sub max/ was 0.0l6, and the corresponding void fraction was 42%. In view of these large changes in neutron multiplication, calculations were made to determine what additional materials could be used in the island to reduce DELTA k/sub max/ and what the associated decrease in peak thermal flux wouId be. The results indicated that of the materials considered the use of beryllium in the water island resulted in the smallest decrease in flux for a specified DELTA k/sub max/. To reduce DELTA k/sub max/ to 0.01 required 26% by volume of beryllium in the island; the corresponding reduction in thermal flux, as compared to an all-water island, was about 10%. In order to reduce DELTA k/sub max/ to 0.0l with a 300 g Pu target in the island, the aIuminum-to-water ratio of the target had to be …

This document presents the total control aspects of the current blanket and central zone E-N loading at H Reactor based on the calculational parameters in Physics of E-N Load compared to Natural Uranium Load at H Reactor, D.I. Monnie, May 11, 1961. The original charge for the E-N core load at H Reactor, (19.37 in. E to 1 in. N) was found to be more reactive than desirable for maximum production efficiency. Therefore a less reactive E to N ratio (18.14 in. E to 1 in. N) has now replaced the original loading.

Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.

BS>Data from examination of blade-type control rods which were used in BORAX are discussed. Operation and maintenance of EBWR is outlined. In work on Borax V, modifications for easier installation of reactor and components is outlined followed by discussion of superheat fuel element development, and fabrication of various reactor components. Borax reactor design is also reported along with information on development and testing. In research on sodiumcooled reactors, activities are summarized in the LPR III and LPR IV programs along with developmental work on EBR I and II. Studies on reactor safety are reported and activities in a program of nuclear technology and general support are outlined. (J.R.D.)

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Report issued by the APDA over a design study "of a facility for testing sodium-cooled thermal reactor fuel assemblies in the Advanced Test Reactor" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.

Abstract: The design and application of two computers for the HNPF protective system is discussed.