Results are presented of research and development work performed in conjunction with the 70-Mw design of a sodium-to- sodium intermediate heat exchanger and a sodium-to-water steam generator. Kanigen plating was substituted for Inconel overlays. A program to evaluate this plating was undertaken. Elimination of tube end ferrules, mechanical behavior of sine wave tubes, tube-to- tube sheet welded connections, metallurgical examination of bimetallic tubes, transition weld test, bayonet tube test, and bayonet tube weld cap test are discussed. (M.C.G.)

A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)

The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit use of gases other than helium. It was further directed that the reactor should be designated BORE for Beryllium- Oxide Reactor Experiment. Reactor development work was mainly in connection with the BORE preliminary design. It was established that the most important information which could be provided by a 10 Mw(t) reactor experiment would be on performance of fuel elements and moderator bodies. This required that the experirment duplicate the power density in the fuel and moderator that would exist in the full size reactor and made it advisable to use full length fuel elements. This resulted in an unconventionally shaped core which is roughly cylindrical with the length more than twice its mean diameter. Studies continued on performance of fuel …

The projected E-N load at H Reactor will require a complete change in the type of charge placed in most flattened zone process tubes. Objective of this test is to determine the reactivity of the proposed E-N charge relative to the known natural uranium charge reactivity.

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From foreword: This report investigates the economics and performance of alternate cycles for heavy water moderated power reactors.

Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.

Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.

To permit either the irradiation of two defected UO{sub 2} four-rod-cluster fuel element assemblies during the same operating period, or the irradiation of the two assemblies singly during two different operating periods in KE Reactor front-to-rear test hole 3865. The density of UO{sub 2} in one fuel element assembly is 90% of theoretical, in the other 87%. In both assemblies the fuel element cladding is Zircaloy and the fuel material natural uranium. An artificial defect will be made in each assembly before irradiation by drilling a .005 in. diameter hole through the cladding near the mid-point of two of the rods in each assembly, thus a total of eight UO{sub 2} rods, four defected and four nondefected, will be irradiated.

This document details activities of the Fuels Preparation Department during the month of May 1960. (FI)

Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).

Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.

Results of a survey covering the safety, adequacy, and reliability of certain design and construction features pertaining to the NS Savannah nuclear power plant and related systems are presented. (auth)

One of the uncertainties concerning the use of uranium-10 wt.% molybdenum in the ORNL Fast Burst Reactor is the thermal-cycling behavior of this alloy. Accordingly, an experimental program was undertaken to determine whether transformation or distortion of gamma-phase uranium--10 wt.% molybdenum can occur during simulated fast-burstreactor thermal cycling, and, should transformation occur, to establish the thermal cycling behavior of partially transformed uranium- - 10 wt.% molybdenum. Specimens were prepared by vacuum casting pins in coated- graphite molds, homogenizing the castings at 1650 deg F for 24 hr, and centerless grinding and cutting to 0.158-in. diameter by 1.5 in. long. The pins were sealed in evacuated Vycor tubes, heated rapidly both above and below the gamma- transformation temperature. and then cooled slowly to simulate reactor thermal cycling. Measurements of the time required to initiate transformation by conventional isothermal methods were employed to insure that the alloy material behaved as indicated in the literature. Observation of changes in appearance, dimensions, density, resistivity, and metallographic structure were used to obtain the desired information. It was found that thermal cycling did not cause growth or distortion of either gamma-phase or partially transformed uranium-- 10 wt.% molybdenum pins. Transformation of gamma phase to alpha + …

The following report is the final safety analysis report for the Task 2 Radioisotope Powered Thermoelectric Generator prepared by The Martin Company. It presents analyses, tests and evaluation of the operational safety criteria for the generator.

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Studies were made to ascertain what useful satellite and/ or space missions may be accomplished with the SNAP 2, 8, and 10 power systems within the 1960 to 1970 time period, to delineate useful satellite and/or space missions which would most profitably employ nuclear power sources, to ascertain what restrictions are imposed on various payloads as a result of having a nuclear power system on board, and to investigate the general vehicle integration and installation requirements of the SNAP 2 and 10 power units. Space flight programs, characteristics and limitations of SNAP, applications of nuclear power supplies. design integration, and system integration are discussed. (M.C.G.)

Report of the daily cash position for Sugarland State Bank.

Daily cash report for Imperial Sugar Company including a list of large withdrawals for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.

Imperial Sugar Company raw sugar handling expense report.

Daily cash report for Imperial Sugar Company including a list of large withdrawals for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.

This report describes Purex Plant operations at Hanford for January, 1961-- December, 1961. Solvent extraction and ion exchange processes and data are discussed.

Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear superior to other types for use with the types of graphite investigated. Experimental measurements were made of the thermal conductivity, tensile strength, stress-strain reiationships, and thermal expansion of graphite powdsr bonded with baked carbon at a final firing temperature of 760 deg C. Results showed that these materials were stronger and more isotropic at all test temperatures than a standard structure graphite such as ATJ. The thermal conductivity is somewhat lower and the thermal extansion slightly higher than the corresponding properties of ATJ. A silicon-silicon carbide coating was developed as an osidation-resistant coating for graphite. Preliminary air oxidation tests at 1000 deg C showed that the first samples survived 2000 hr with 10% failure. Subsequent experiments showed that it is reasonable to expect better performance in further tests. Tests for compatibility with …