Cerium sulfate purified by D2EHPA in Semiworks can be precipitated by adjusting pH to between 1 and 2 in tank 6 with 50% caustic. The solution can then be transferred through tank 1 to tank 67, where sodium bisulfate is added to make the solution 0.5M sulfate. A stoichiometric amount (mole for mole) of 50% caustic is added to just neutralize the sodium bisulfate. The precipitate is digested one hour at 60 C, then filtered.

Reference (2) requested that we review the possibilities that classified information might be revealed by isotopic composition of fission products, and suggest methods of making any such compositions. These questions have been reviewed thoroughly by Hanford Laboratories experts; their analysis confirms earlier conclusions (Reference 1). Based on current classification guides, isotopic compositions of cesium, promethium, and probably other rate earths could reveal secret information. Unless classification rules are changed, we see no way to declassify these fission products except by blending them with unclassified products from other sources.

The steadily increasing graphite stack distortion in the K Reactors has caused serious operating problems with the existing horizontal control rods. To compound the seriousness of the problems, the high level of reactor operation today and the anticipated higher level of operation in the future demands a reliable control rod system. A flexible control rod has been designed by Reactor Design, IPD, to facilitate reliable operation of the HCR system in spite of channel bowing arising from graphite stack distortion. This flexible control rod design is radically different from the existing K Reactor control rods and in fact, is more closely aligned to the control rods now in use at the older Hanford Reactors. The major difference of the new rod is the elimination of intimate contact between the poison-containing section of the rod and the cooling water. Such a change in design as described above could result in significant changes in the operating temperatures of the rod proper. This study was undertaken to provide a calculated indication of the temperature changes and the relative magnitude of such changes relative to reactor power levels, graphite temperatures, coolant temperatures, etc. In addition to this basic information, the scope of the study …

This production test authorizes the irradiation of full length charges of solid aluminum in the KER loops while on single-pass operation with process water cooling. Calculations show that the irradiations will not result in any foreseen reactor or personnel hazards and can be safely performed in the KER facilities.

At present there seem to be some uncertainties concerning the needs of rupture detection for the co-producer programs Also in question is the method by which ruptures of the target elements should be detected and located. The purpose of this report is to discuss the waste and hazard control of tritium (H{sup 3}) (the product of the co-producer program), which will determine rupture detection needs, and to discuss methods by which rupture detection and location may be accomplished. The scope of the report considers first, adaptation of the present rupture monitoring system, and second, monitoring systems using H{sup 3} analyzers, together with the costs and time required to develop and use each method of rupture detection.

Approximately 285 ribbed aluminum process tubes will have been installed in the central zone of each K reactor on completion of the zirconium tube replacement program. This report recommends the use of mixer fuel elements in the ribbed tube and discusses the basis for the recommendation. The recommendation is complicated by the fact that two tube designs having different dimensions will be used and the optimum mixer location for the two tube designs is different also.

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The stability of the circulating beam in a radiofrequency system with large beam loading is investigated. The results are applied to the 3-Bev electron-positron storage ring under design at the Cambridge Electron Accelerator. It is found that for this type of system, in which there are no large transients, it should be possible to use most of the radiofrequency power to supply the radiation losses of the circulating beam and only dissipate a small fraction of the power in the r-f cavities. (auth)

The initial 30-Mw SRE Core III loading will contain a total of 33 fuel elements. Of these, the central 7 fuel elements are test elements and the remaining 26 are driver elements; 4 of the 7 test elements are designated as standard test elements. These elements are identical to the driver elements with the exception of the active fuel length. The remaining 3 test elements are designated as special test elements and incorporate fuel rods of smaller diameter and increased enrichment to obtain higher burnup rates, greater specific power, and higher fuel temperatures. Geometry design data for the various elements considered in the analysis was obtained from Dwg. No. 650 deg F, the mixed-mean coolant outlet temperature for the core at 1200 deg F ( plus or minus 15 deg F), the maximum average temperature on the cladding at 1275 deg F, and the maximum fuel temperature in the range of 2000 to 2100 deg F. The thermal performance of the fuel elements was analyzed with the SORTD code and the Heating code. The results of the analysis are presented in tabular form. Axial temperature profiles are also presented for representative fuel elements. The core outlet coolant mixed-mean temperature was …

BS>When radiation shields are penetrated by ducts, the gamma rays resulting from the radiative capture of lowenergy neutrons in the duct walls can be principal contributors to the total dose along the duct. In order to calculate the effect of these capture gamma rays, the distribution of low-energy neutrons in the ducts must be known. This report presents calculations of low- energy neutron distributions in concrete-walled ducts by a method in which an albedo model and a Monte Carlo technique were used. One series of calculations was performed for straight ducts so that comparisons could be made with the Simon- Clifford analytic approximation. Another series was for threelegged rectangular ducts similar to those used in a Tower Shielding Facility experiment. When au albedo similar to that to be expected for a pure thermal-neutron source was used, the results agreed very closely wilh the TSF data. A digital computer code was written to perform the calculations. (auth)

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This document is a user manual for those who are familiar with problems 500 Node Transient Heat Transfer Code.

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