Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.

None

Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added to the combined wash solution and filtrate produced during the precipitation step to destroy the formate ion (which inhibits uranium extraction) and to prevent post-precipitation during the evaporation of these solutions. The other flowsheet calls for addition of sufficient nitric acid to destroy the formate ion, but not enough to prevent post- precipitation during the concentration step. Post-precipitation removes additional zirconium and fluoride, but necessitates an additional solids- separation step. (auth)

A number of conceivable reactivity accidents were analyzed, using conservatively pessimistic assumptions and approximations, to permit evaluation of reactor safety. Most of the calculations, which are described in detail, were performed by a digital kinetics program, MURGATROYD. Some analog analyses were also made. None of the accidents which were analyzed lead to catastrophic failure of the reactor, which is the primary consideration. Some internal damage to the reactor from undesirably high temperatures could result from extreme cold- slug accidents, premature criticality during filling, or uncontrolled rod withdrawal. Each of these accidents could happen only by compounded failure of protective devices, and in each case there exists means of effective corrective action independent of the primary protection, so that damage is unlikeIy. The calculated response to arbitrary ramp and step additions of reactivity show that damaging pressures could occur only if the addition is the equivalent of a step of about 1% delta k/k or greater. (auth)

Research and development of water-cooled reactors are reported including work on EBWR and BORAX-V. Work on liquid metal cooled reactors is also reported in sections on general research and development, EBR-I and II, aud FARET. Other work is reported on genenal nuclear technology and advanced systems development. (J.R.D.)

Tin-- aluminum base coatings applied by a cold spray-hot vacuum diffusion technique were studied further on Ta-10 W and Ta-10 Hf-5 W and work initiated on Ta--30 Nb--7t/2 V. Refractory additions to the coatings were optimized for Ta--10 W and the use of aluminum-silicon in tin was found beneficial for Ta--30 Nb--7 1/2 V. Furnace and oxy-acetylene torch tests were performed at temperatures from 1100 to over 3000 deg F. Diffusion treatments in vacuum, hydrogen, and argon were compared for coatings on Ta-10 W. Oxide formation on Ta--10 W coatings at various temperatures was studied by x-ray diffraction. The oxidation behavior of various tin--aluminum alloys and of the intermetallic (Ta--30 Nb--7 1/2 V) Al/sub 3/ was also studied, together with interactions of three alloys with A/sub 2/O/sub 3/ at elevated temperatures in vacuum. (auth)

Considerable interest has been generated concerning the recent series of overbore fuel failures at C Reactor. It therefore is appropriate to document the operating conditions which existed prior to the failures. This report presents a chronological description of events leading up to the failures, and graphs and tables of various pertinent parameters.

In this report, approximations which have been shown to simplify the calculation of the normal modes of paraffin hydrocarbons are tested for olefinic hydrocarbons by application to C2H4, CH2CD, C2D4. The results indicate that the method should suffice for the low-frequency models below about 0.1 ev energy, and may be adequate for all vibrations as far as he needs of neutron scattering are concerned,

This volume is one of twenty-one summarizing the Aircraft Nuclear Propulsion Program of the General Electric Company.

This document presents a summary of work and progress at the Hanford Engineer Works for April, 1962. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services Departments have sections presenting their monthly statistics, work, progress, and summaries.