This report addresses the advanced energy sources and conversion techniques.

In an experimental program recently completed at the 184-inch synchrocyclotron in Berkeley, data were obtained on elastic {pi}{sup +}-p scattering at a laboratory energy of 310 Mev. Quantities measured were the differential cross section, the total cross section, and the polarization of the recoil protons as a function of center-of-mass angle. We have analyzed the data in terms of S, P, and D waves and have obtained only one acceptable solution. The resultant set of phase shifts is of the Fermi type. The D-wave phase shifts are small but definitely needed to obtain an adequate fit to the data. Owing to the relatively high accuracy of the cross-section data and the inclusion of the results of the polarization experiment, the errors on the small phase shifts have been reduced to less than 1{sup 0}. The differential cross-section and polarization data are given in Tables I and II.

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Data were obtained to evaluate the attenuation of photons, emitted from a fallout field, due to the surface roughness of the terrain. A study was made to determine the effect of the shot tower on the fallout material. Particles for comparison were collected from two detonations of equal scaled height, one tower supported and the other balloon supported. Data on time-dependent phenomena were recorded, as were physical characteristics of the fallout material. The use of small balloons as instrument platforms and a new fallout collector were evaluated for field use. No conclusions or recommendations can be made at this time.

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The minimum shutdown time, to permit accessibility, for the Intermediate Power Reactor is estimated to be 38 hours. In case the reactor were shutdown following each rupture this long shutdown period would have serious disadvantages. The desirability of being able to make firm power commitments (independent of slug ruptures) has led to a study of the possibility of continuous operation following a rupture. There is evidence to indicate that, at the proposed water temperature, the rate of corrosion of uranium may be so high that at least a major portion of the rupture products may have entered the system before the reactor can be shutdown. A pushout of the affected column would then be a pushout of only those slugs which are still intact and the problem would still remain of removing the rupture products from the system. The first portion of this report is concerned with the rate of corrosion of a slug following rupture and the possible limitations to the principle of non-shutdown operation. These limitations include a flow stoppage by the ruptured can, undue increase in gamma activity, increased corrosion by the rupture products, and adherence of rupture products to the piping. The latter portion of the …

The attached document includes a plot plan, flow diagram and delineation of basic assumptions upon which the report was developed. It summarizes the work which has been accomplished to date under RDA No. DC-6 in developing a recirculating water system to serve a new reactor. In order to proceed with the work under RDA No. DC-6 it has been necessary to make certain basic assumptions relative to the primary circuit requirements of RDA No. DC-3. These assumptions are explained in the report and are presented by the exhibits contained therein. Subsequent to the compilation of the basic report certain additional considerations have come to the authors attention and are included in the addendum.

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This document discusses waste disposal criteria were established on the basis that the occurrence of river flow rates which were 72 cents of normal would not cause the effects of waste disposal to exceed limits. Since even the base case exceeds the criterion for the average body burden of phosphorus-32, provision to reduce the output of this radioisotope must be included in any expansion program. Provision to reduce the output of other radioisotopes will be required for most cases where the bulk outlet temperature limit is 105{degrees} or higher. For reactor flow rates exceeding 100,000 gpm it may be necessary to reduce sodium dichromate concentrations as low as 1.5 ppM during periods of low river flow. Heat output was discussed but no limit was set.

Mechanization of the 300 Area slug canning facilities is required to obtain uniform high quality product and to eliminate variables introduced by the human element. The work to be covered by this brochure will cover requirements for mechanization of only the operations occurring within the aluminum-silicon canning bath: can and cap preheating and wetting, canning assembly, and quenching operation. Briefly, this machine will be required to insert a prepared uranium slug into an aluminum can and close the can opening with an aluminum cap. All assembly operations are to be carried out underneath a molten bath of aluminum-silicon bonding alloy. The uranium slug is preheated and prewetted before being transferred to the assembly furnace; however, the process must be so timed that proper preheating and wetting is attained before the slug is inserted. After assembly the completed canned slug is transferred to the quenching station, where the components are to be firmly held together until the molten Al-Si has frozen, forming a homogeneously bonded assembly.

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This report discusses a system which has been conceived whereby additional flexible reactivity control in the production reactors can be achieved by introducing neutron absorbers contained in thin flexible metal strips between the slugs and the process tube wall. These splines are potentially attractive in that it is possible they could be used to provide additional flexible control during operation as well as temporary control during outages.

This report discusses Production Test 105-516-A which was written to determine the stability by both measurement and visual examination, of thorium slugs as used in flattening columns to exposures in excess of 400 MWD/AT. Both rolled and extruded thorium slugs were used; the highest exposures reached were about 1000 MWD/AT. Also discussed is Production Test 105-551-A which was written to demonstrate the stability of thorium slugs as used in flattening columns at exposures up to approximately 1500 MWD/AT; the supplement authorized exposures up to 3000 MWD/At. Six tubes of 10-66 material already in the pile were chosen; these have been discharged at exposures varying from {approximately}1230 to {approximately}2000 MWD/At.

If material received under this program is deemed acceptable for reactor charging, this test will authorize irradiation of fourteen monitor columns which shall be discharged at 200, 400 and 800 MWD/T to observe the performance of this material. This test shall run concurrently with irradiation of quantities up to 60 tons/month to be authorized separately.

Twenty charges each of low hydrogen dingot fuel and standard ingot fuel elements were irradiated at DR-reactor. Distortion data from 22 tubes are analyzed in this document. The dingot fuel elements are prone to greater tube filling capacity (TFC) and greater daimeter growths at both center and ends of the fuel elements (the growths at center are larger than at ends). The difference between average warp values for the two types of fuel elements is not statistically significant, indicating that the greater TFC values shown by th dingot fuel elements are due to their larger diameter growths at the slug center rather than to larger warp values.

This document presents a summary of work and progress at the Hanford Engineer Works for October 1951. 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.

This report details initial results of a large scale accountability test program which was recently carried out in the Redox Facility. The test, as originally planned which was to consist of the complete processing (no inventory-clean plant basis) of about 55 tons of selected metal in conjunction with an extensive analytical, sampling, and volume measurement program. With the exception of two incidents, the processing requirements (minimum inventory and measurement of all material) necessary to the success of the test, were met. The two incidents which increase the uncertainties associated with some of the material balance values obtained were: the discharge of an estimated 700 pounds of uranium to the floor in a transfer from F-5 to F-4 due tot he improper installation of the F-5 to F-4 transfer line (jumper) and the discovery of a large accumulation of plutonium ({approximately} 15 kg) in the L-2 stripping tower after completion of the test run.

Four Zircaloy-2 jacketed enriched seven-rod cluster elements, one three-foot three-rod Zircaloy-2 jacketed enriched cluster element with integral end closures, and two eighteen-inch Zircaloy-2 jacketed wire wrapped cluster elements containing UO{sub 2} will be irradiated at jacket surface temperatures up to 270 C in the KER loops to an exposure of 3500 MWD/T on the enriched seven-rod cluster elements.

Laboratory data of flow rate versus header pressure were obtained for various conditions of nozzle cap removal from C, K and BDF single tube mockups of central zone tube assemblies using I&E slug charges. The data are presented. Suggestions are made for applying the data to DR and H reactors. In general, the effect of a pre-inserted support charge on the flow rate is small, especially with the front nozzle cap on. It should be noted that pre-insertion of an entire (117 inch long) support charge and subsequent front cap replacement is impossible in either a BDF tube with 34 fuel elements or a C tube with 32 fuel elements simply from a length standpoint.

This report records the basis underlying the decision already reached to recommend a change of process tube fittings at B, D, F, DR and H reactors, and also proposes for consideration a change in the devices for monitoring effluent water temperature.

The Process Specifications for Operational Control of the Purex Plant(l) have been revised to define the operational control changes as a result of (a) converting the Purex Plant from three to two cycles, and (b) the use of the Plutonium Anion Exchange Unit (N-Cell) for routine plutonium concentration in place of the L-Cell Concentration Package. The flowsheets specified in Figures I-1, -2, and -3, and Table I fulfill the requirements for nuclear and chemical safety within the process as defined in Purex Process Specifications. The flowsheet also provides adequate recovery and decontamination to meet the product purity requirements itemized in Section 3.04. To clarify the two-cycle flowsheet and to simplify its use, the specifications are listed on graphic flow diagrams with the notation that process control allows a deviation of plus or minus five percent on all specifications except TBP concentration in solvent.