In the production of plutonium in a reactor, plutonium-238, 240, and 241 are formed as well as Pu{sup 239}. It is well known that the specific alpha activity of the plutonium varies as the percentages of these isotopes are changed. Kinderman, et al have worked out the relationship between isotopic content and MWD/ton exposure. Their findings are reported in this document.

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 is a supplementary operating guide to document HW-44064, ``Process Specifications for Critical Mass Control -- Purex Plant.`` It is primarily intended that this document illustrate the actual operational means of conforming to the limits of critical mass control as presented in HW-44064.

This memorandum discusses experimental determination which was made of the sensitivity and operational characteristics of the modified effluent water beta activity monitor system which is to be utilized at C pile for slug rupture detection. The optimum operating conditions for this system were also determined. A comparison of the performance of the C pile system with that of the existing Hanford type beta system was made to establish the degree of improvement realized through system redesign; this information being of assistance to the Pile Physics slug rupture detector development program. This report discusses the performance of both beta sensitive systems and the parameters upon which improved performance depends. A two ionization-chamber mockup of the C pile system was installed in the near effluent water sample room at H pile and utilized in these studies.

The purpose of this report is to present the conclusions and recommendations obtained during the course of the CPD Control Study and the conceptual framework upon which they are based. Primary emphasis has been given to the control of product materials. In order to logically present the background for the definition and delineation of an appropriate CPD Control System, Section III of this report discusses a control system in the following manner; (1) the description of the control system information requirements, (2) the definition of the conceptual framework of product material control, (3) the discussion of the interrelationships of production scheduling, process control and accountability and (4) the methods for the effective utilization of control system information. Section IV utilizes this conceptual framework in order to enable a logical presentation of a proposed product material control system for the CPD. A summary of conclusions and recommendations is included in Section II. The Appendices consist of discussions of specific analysis conducted during the study. Other related reports that have been issued during the course of the study are included in the references.

Side rupture data experienced to date for I and E fuel elements give rupture rate curves which do not differ significantly from those predicted on the basis of solid fuel elements experience.

A. M. Gaudin and collaborators have published a curve of refining costs versus ore grade in terms of dollars per pound of U308 recovered on the basis of 90% recovery.

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In order to obtain data for the development and design of the Purex dissolvers and to demonstrate to Manufacturing and Technical personnel the feasibility of increasing the size of dissolver cuts at BiPO{sub 4} and Redox, a dissolver production test program in a BiPO{sub 4} dissolver is requested. These tests are expected to supplement the program already initiated on the 321 Bldg. dissolver, explaining dissolver behavior to the extent that existing dissolvers can be operated under more nearly optimum conditions and that new dissolvers can be designed with accuracy.

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The loading on the primary transformers which step down the 230 kv transmission voltage to a distribution voltage of 13.8 kv, at 100-B-C, 100-D-DR, 100-F, and 100-H Areas will be increased by the synchronous motors now being installed in those areas under Project CG-558. This report summarizes: The changes in electric loads (both kv and power factor) which will result when the new motors are placed in service and certain older motors are withdrawn from service. Electric loads are tabulated in section 4.0 for each area for present conditions, the planned changes and the post-CG-558 conditions. The reduction of distribution voltage during the starting of individual 4500 hp synchronous motors. Since the synchronous motors will be started across the line as induction motors, the starting current will be high, and at a low power factor. Voltage drops are calculated for the starting of a synchronous motor, with one and then with two transformer banks paralleled. The current-interrupting capacity of switchgear vs. the maximum short-circuit current which could occur with separate transformers and with two primary transformers in parallel.

A project proposal is now under preparation for converting all areas to the alum and activated silica coagulation process, and modifying the present test installations to permanent facilities. The conversions will be designed to service increased water flows resulting from the reactor plant expansion program now under way. As an alternate to the installation of permanent facilities at the various areas, the possibility of hauling already prepared activated silica from those areas having excess capacity to those areas requiring large capital expenditures was suggested. The purpose of this study is to make an economic evaluation of the operating costs of hauling activated silica compared to the increased capital investment necessary to manufacture activated silica at various areas.

The Bevatron is still undergoing a process of gradual improvement to increase both the magnitude of the beam and the reliability. The operating conditions for optimum adjustment at the present stage of development are summarized.

Corrosion of aluminum front cap supported shielding slugs has been noted at all reactors except C Reactor which has galvanized shielding pieces. There has been a considerable amount of difficulty caused by sticking of the places. The difficulty is caused by the growth of corrosion products in the annulus around the shielding piece which affectively siezes it. As recently as June, 1953 the shielding pieces on nearly 50 per cent of a group of 40 tubes at B Reactor were corroded to the extent that a pipe wrench was required for their removal. Similar instances, to varying degrees, have occurred at all reactors except C.The purpose of this test was to evaluate the radiation affects of removing the front shielding pieces as part of a program to eliminate the sticking problem.

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This document addresses questions concerning radioactive build-up in a liquid control solution recycling through the pile at the Hanford Works plant. The solution composition and method used to obtain dose rates are included.

It is recommended that the Design Committee approve the installation of a refrigeration system in the 105-C gas circulation system for removal of moisture from the reactor following a process tube leak as was previously approved by the C-431 Project Committed. Engineering studies show that this refrigeration system is necessary to provide sufficient water removal capacity in order that the water absorbing capacity of the system furnished by the silica gel towers will not be a limit to the rate at which a reactor can be rehabilitated following a serious leak.

Two important problems in the investigation of reactor hazards are the chemical reactivity of various materials employed in reactor construction and the chracteristics of heat transfer under transient conditions, specifically heat transfer when driven by an exponentially increasing heat source (exp t/T). Although these problems are independent of each other, when studied in relation to reactor hazards they may occur in a closely coupled sequence. For example the onset of a dangerous chemical reactor may be due to structural failure of various reactor components under an exponentially rising heat source originating with a runaway nuclear reactor. For this reason, these two problems should eventually be studied together after an exploratory experimental survey has been made in which they are considered separately.

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A kinetic study of the accumulation of C{sup 14} in the intermediates of steady state photosynthesis in C{sup 14}O{sub 2} provides information regarding the sequence of reactions involved. The work described applied the radio-chromatographic technique for analysis of the labeled early products. The simultaneous carboxylation reaction resulting in malic acid as well as phosphoglycerate is demonstrated in experiments at high light intensity. A comparison of radioactivities in a number of phosphorylated sugars as a function of time reveals concurrent synthesis of fructose and sedoheptulose phosphates followed by that of ribulose phosphates and later by that of glucose phosphates. The possibility that the cleavage of C{sub 4} compounds to C{sub 2} carbon dioxide acceptors may involve C{sub 7} and C{sub 5} sugars and evidence for this mechanism is presented.