Present thinking and planning appears to be developing from the following factors as concern the 13.8 KV temporary construction power limit. 1. It is understood that the present intent is to supply 100-N operating requirements from a single stub source in the 230 KV loop. 2. The original thoughts were to obtain construction power over a 13.8 KV line from 151-D substation. 3. Construction load requirements are now less than originally planned since steam has been substituted for electrical drive of primary loop pumps and 5500 hp motor tests are no longer necessary. 4. An extreme emergency backup source for the K plants has always been of concern, although minimized in recent planning. It is desirable to review the temporary construction line requirements from a future operating viewpoint to determine if the line could be useful to the operating plants after completion of construction. It is highly desirable to provide T.C. power source from K plants rather than 151-D and then leave the line and breakers in place for future maintenance assistance and as extreme emergency backup to K plants.

This document is Revision No. 2 of the ``Process Specifications for Critical Mass Control -- Purex Plant``. It encompasses the changes in flowsheet, equipment and plant operating philosophy that have developed since the plant startup. It supersedes Document HW-44064 (Revision No. 1). Plutonium-239 and uranium-235, either as the metals or as dissolved or solid compounds are capable of spontaneous and violent nuclear reactions. Following initial dissolution of irradiated natural uranium fuel elements the Purex Plant is normally involved in the processing of liquid solutions containing these isotopes. However, in Purex Plant solutions, uranium-235 is invariably associated with a large fraction of neutron-absorbing uranium-238, a condition which precludes the possibility of a nuclear reaction. (These specifications are based on the premise that no enriched uranium is processed in the Purex Plant.) Plutonium-239, on the other hand, is separated from uranium by means of the Purex process; and even prior (process-wise) to its separation, the ratio of plutonium to uranium must be controlled during the off-standard conditions of plutonium rework or recycle. Critical mass control in the Purex Plant is concerned solely with prevention of nuclear reactions of plutonim-239, which has been produced by irradiation of natural uranium fuel elements.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: What is the General Statutory authority of the Board for Texas State Hospitals and Special Schools to establish the Central Multilith Service, the Motor Pool and the Central Supply Service, and related question.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: May funds from the State Hospitals Building Fund be used for the purchase of a site for out-patient facilities at Dallas and San Antonio? May a portion of the same funds be used for the construction of out-patient facilities at Dallas and San Antonio?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a drawing for prizes constitute a lottery where some of the tickets are given with purchase of merchandise and some of the tickets are given away free.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Payment of Special Commissioners in Condemnation Suits.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Are the so-called "family group" life insurance policies being submitted to the State Board of Insurance contrary to the provisions of Article 3.50, Section 4, of the Texas Insurance Code, and related questions.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Should the Secretary of State accept and file Articles of Incorporation in which the corporate name includes one of the words, "discount," "rediscount," "guaranty," or "surety," and related questions.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Authority of and procedure for the leasing of land of the Alabama-Coushatta Indian Reservation in Polk County, Texas for oil and gas development.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: May the Texas Water Development Board lawfully give financial assistance to a political subdivision for the construction of a water filtration or water treatment plant when such plant constitutes an integral part of the entire water project?

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Authority of Commissioners Court of Rusk County in Redistricting Justice of Peace Precincts and related questions.

This report describes the second part of an IBM 704 Computer Code to determine transient thermal stress in pressure vessels. This part computes stresses from temperature distribution determined by the first part. A brief account is given of the solution of axially symmetric thermal stresses, using harmonic stress functions. This is followed by a description of the Code and complete input and operating instructions for a number of problems: a. Transient temperature distribution due to sudden change of temperature. b. Transient temperature distribution due to surface temperature changing as a function of time. c. Thermal stresses for temperature problems ( a ) or (b). d. Thermal stresses due to previously known temperature distribution. The code is known as TURF6. It was found that the computer results for thermal stresses in a solid sphere subjected to a sudden change of temperature at the surface corresponded within 5% of the theoretical values. The IBM 704 Computer required for this code has a 16 K memory, three drums and two tape units.

The schedule for the installation of the PAR slurry loop experiment in the South Facility of the ORR has been reviewed and revised. The design, fabrications and Installation is approximately two weeks behind schedule at this time due to many factors; however, indications are that this time can be made up. Design is estimated to be 75% complete, fabrication 32% complete and installation 12% complete.

To date, no data is available on the swelling rates of unrestrained unalloyed uranium rods operating at 450--630C core temperature and 250--350C surface temperature. These temperature ranges are of extreme interest in the Hanford fuel element development program. To obtain information on the effect of cladding restraint, exposure, and the above temperatures, on uranium swelling rates, a series of experiments is being designed for irradiation in Hanford reactors. The experimental assembly consists of a uranium fuel rod supported concentrically in an aluminum capsule. Surrounding the fuel rod is an annulus of liquid NaK to serve as a heat transfer agent. To provide a check on the operation and temperature calculations of the capsules, it is proposed initially to make a single irradiation in a normal process tube. The uranium core temperature will be continuously monitored by a thermocouple, and flux measurements will be made in the capsule to determine the specific power of the fuel.

Since the New Production Reactor is to have higher power density than the existing reactors, graphite contraction is a critical factor in its design. Ample data are available to describe graphite distortion in certain temperature ranges in the HAPO reactors. H Reactor exhibits three distinct and increasing contraction rates, corresponding to 3 levels of equilibrium power. A small temperature dependence may exist. There is no evidence of saturation of graphite contraction in the HAPO reactors. Extrapolation of the current trends are made. Programs are underway to further define graphite behavior and to solve problems associated with graphite distortion.

None

None

Bubble phenomena have been given a new meaning with their study in relation to the kinetic behavior of reactors. Prior to their study in relation to physics, the bulk of work on bubble phenomena concerned naval engineering problems of behavior in cavitation and water entry behavior. This bibliography is intended to fill the need of the reactor physicist as well as the naval engineer. An attempt has been made to include all available references on bubble phenomena and associated effects. A subject index has been purposely omitted. It is felt that the breakdown in content headings is sufficient to ascertain areas of interest. There will be overlapping of headings and to find all possible entries, a search through the headings may be desirable. To increase the usefulness of this bibliography the location of an abstract has been cited wherever possible following the reference. Classified reports are included; however, their titles contain no classified information. Sources used in compiling this bibliography are: Chemical Abstracts, Industrial Arts Index, Applied Mechanics Review, Nuclear Science Abstracts, the AEC Abstracts of Classified Literature, the AEC card catalogs available at Atomics International, and the bibliographic services of Armed Services Technical Information agency. (auth)

A thermoelectric generator having independent outputs of 1.2 and 4.8 volts at more than 50 milliwatts after six month's service has been constructed and tested using a mock Po/sup 210/ heat source with an initial thermal power of 37 watts. (for preceding period see MLM-CF-58-4-49.) (auth)

Approximately 1,000 references to technical reports on nuclear and conventional merchant ships are cited. (T.R.H.)

A preliminary definition of a fabrication process for ferritic stainless steel-UO/sub 2/ fuel clad with Type 430 stainiess steel has been achieved. The procedure is an adaptation of an earlier process for preparing austenitic fuel elements, and consists of the cold-binder extrusion of a plastic powder dispersion which is fired in dry hydrogen, fitted with welded end caps, and electroplated with nickel. This core is inserted into a length of type 430 stainless steel cladding and the assembly is bonded by hot-swaging at 800 C. The irradiation performance of such a fuel element was examined by means of an MTR test. The results of this test strongly indicated that the desired lowering of UO/sub 2/ particle operating temperature was realized and that ferritic stainless steel is not unduly susceptible to irradiation dannage. (auth)

An investigation has been begun of interdiffusion in the aluminum- uranium system and of the effects thereon of applied pressure. In confirmation of the results of other investigations, it has been found that UAl/sub 3/ layer growth is accelerated by increasing applied pressure. The growth kinetics are characterized by a transient'' period, during which growth occurs non- parabolically, which is followed by a steady state'' period of parabolic growth. Interesting correlations are shown to exist between annealing time, annealing temperature, and applied pressure on the one hand, and the nature and distribution of structural defects in the UAl/sub 3/ diffusion zone. (auth)

None

S>Progress is reported on fuel element development, reactor mechanical studies, nuclear analysis, chemistry, control, safety, feasibility, steam cycle, and materials and metallurgy. (For preceding period see AECU-3683.) (T.R.H.)