This report is the third in a series of quarterly reports discussing the concept and progression of an improved method in nuclear measuring than the usage of the scintillation counter. This report indicates that in a chopped double beam system, commutation of the detector current permits selection of optimum response time and size of radioactive sources.

Since startup in January 1945 through December 1959, 4 {times} 10{sup 9} gallons of radioactive liquid wastes have been discharged to cribs and trenches at HAPO by the Chemical Processing Department facilities in the 200 Areas. These wastes contained approximately 2.5 {times} 10{sup 6} curies of beta emitters. The Scavenged Waste Recovery Program was completed in 1957 and Redox Plant process changes were made during the latter part of 1958. These changes resulted in significant reduction in the amount of radioactive materials that have been discharged to the ground in subsequent years, from a maximum of 8.2 {times} 10{sup 5} curies in 1955 to 9 {times} 10{sup 3} curies in 1959. Although these large amounts of radioactive materials have been discharged to the ground, periodic waste report inventories include no reduction due to radioactive decay. The estimated depletion by radioactive decay is the basis of this report.

Enclosed is the data that was collected during the recent thermal cycle of KER-1. This data includes the RTD readings and information taken from the thermocouple fuel element. In conjunction with obtaining data on film build-up, the test provided an excellent opportunity to study the effect of temperature on measured tube power. It has been noticed that the KER reactor tubes appear to produce more power (greater {Delta}T) at lower operating temperatures, but the reason for this power increase is not known. With the additional thermocouples to measure water temperatures at the center of the tube, it should be possible to determine if this increase is from the graphite or from the 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: Frequency of compiling delinquent tax rolls.

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: Joint Utilization of Texas National Guard Armory Board Facilities.

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: Under the Texas Hospital Licensing Law, Senate Bill 121, Acts 56th Legislature, Regular Session, 1959, codified as Article 4437f, V.C.S., should all hospitals operated by a hospital district be individually licensed by the State Board of Health, 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: Whether the aircraft of a commercial airline are taxable on an ad valorem basis when such aircraft are based in the county of the company's domicile even though the aircraft fly in interstate commerce.

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: Applicability of the Texas stock transfer tax (Ch. 16, H.B. 11, 3rd C.S., 56th Leg., codified as Title 122A, Taxation-General, R.C.S.) to joint tenancy arrangements under employees' stock purchase plan.

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: Under Art. 297, Penal Code, State of Texas, does the compulsory school attendance period commence on the first day of the opening of the school term unless otherwise authorized by the District School Trustees 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: Would a practitioner who fills prescriptions be required to have a permit from the Texas State Board of Pharmacy and can the practitioner authorize his nurse or aide to fill and dispense prescriptions.

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 the Texas Youth Council has the authority, under existing law, to furnish a prescribed uniform for staff members under their control to wear while carrying our their duties, 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: Legal Status of Texas Public Junior Colleges as regards their eligibility for financial assistance under Title III of the National Defense Education Act of 1958.

It is the purpose of this document to provide assistance to the Manufacturing Section personnel in determining their future operating plans. In general, the inter-relationship of such engineering parameters as flow, reactor orificing, rupture performance, etc. has been considered. The effect of these engineering parameters are summed up in our recommendations for {open_quotes}Operating Plans{close_quotes} shown graphically in this document. It is to be emphasized that these plans do not reflect operational considerations which may modify the desirability of the indicated level increases nor has allowance been made for ability of the indicated level increases nor has allowance been made for major projects, major maintenance outages, or major changes in pile loadings. Many factor, which only Manufacturing personnel are capable of evaluating, may make it desirable to operate below or above these {open_quotes}Operating Plans.{close_quotes} These {open_quotes}plans{close_quotes} are based on incremental metal cost and burnout cost estimates obtained recently from L. W. Lang. A change in these assumed costs would require a revision to be made to these {open_quotes}plans.{close_quotes} It is also to be noted that many of the engineering parameters and basic assumptions which have been factored into these {open_quotes}plans{close_quotes} are subject to continual re-evaluation and revision. Thus, in a strict …

This report details the proposed E-N, tritium-plutonium producing reactor loading is made up of striped columns of lithium-aluminum (mint) target slugs and enriched uranium (.947 w/o U{sup 235}) slugs. Both target and uranium slugs are of the I & E geometry. The ratio of mint (N) to uranium (E) is determined by the requirement of sufficient k-excess to sustain an operable reactor. The designer of the lattice loading has a choice between natural lithium (7-5 w/o Li{sup 6}) or lithium enriched to {approximately} 38.5 w/o Li{sup 6} for the mint slugs, assuming enriched or ``black`` mint is available. It is possible to show at least 0.8% increase in total conversion ratio for an E-N load for enriched mint (38.5 w/o Li{sup 6}) over natural mint. The basis of the calculations rests on measured E-N length ratios for equivalent neutron multiplicative properties for both types of mint (in a dry pile) plus analytical calculations. It is shown that both increased Pu and H{sup 3} production are obtained by using blacker mint. The basic phenomena are (1) increased resonance capture in U{sup 238} due to more uranium volume in the black mint E-N lattice and (2) more efficient utilization of neutrons in …

In 1957 three of the four high temperature recirculating loops in KE Reactor were put into service and in 1958 the fourth loop was started up. The primary purpose of the loops has been high temperature irradiation testing of fuel elements in support of the NPR fuel element development program, although tests have been run to provide information for PRTR fuel development and high temperature aluminum corrosion programs. Coolant technology studies relating to activity build-up, crude formation, corrosion, failure detection, and decontamination are carried on in conjunction with the fuel element tests. The purpose of this document is to provide a resume of all fuel element test irradiations in the KER Loops from the time they started up to the end of CY-1959. A description of each test, its operating conditions, a chronological history of each loop, and a bibliography of documents pertaining to the tests are included. Supplements to this report will be issued periodically to bring the information up to date.

Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were taken and analyzed for uranium, specific gravity, and excess nitric acid. The dissolver charge was digested an additional four hours. At the end of the digestion period, two 1 ml samples and one 20 ml pig sample were taken. The three samples were analyzed for U, SpG, and HNO{sub 3}. Agreement between these samples and the previous samples was taken as confirmation of complete dissolution and representative sampling. If agreement was not obtained, sampling was continued. After verification of the pig sample, six 1 ml aliquots were taken for analysis by the Analytical Control group. The remainder was aliquoted to provide material for mass analysis and for analysis by the Process Chemistry group.

The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.

From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.

Supplement F to Production Test IP-314-A authorized an upstream thermocouple train in KER-1. This document provides fuel element loadings, operating temperatures, and trip settings for two possible charges in KER-1, one using KSE-3 heater elements and the other using KSN-3 heater elements. For a charge containing KSE-3 elements, the loading and the operating conditions are given. For a charge containing KSN-3 elements, the loading and the operating conditions are given. The desired operating temperature and trip settings needed to maintain the maximum uranium temperature below 660 C are given. One of the thermocouples in the thermocouple element, however, indicates the maximum uranium temperature directly. Based on the thermocouple readings, the outlet temperature and trip settings may be set to exceed or fall short of the values designated by the dashed lines provided. The temperatures do not exceed the limitations set by the solid lines which are based on the requirements that boiling will not occur on the fuel elements during normal operation and burnout will not occur at the limiting trip conditions. The maximum uranium temperature shall not exceed 660 C.

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Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.

The Purex Plant was originally designed to operate at a instantaneous rate of 8-1/3 tons of uranium per 24-hour day on a three-cycle flowsheet. Subsequently, the rate was increased to 26-2/3 T/day and the process changed to a two-cycle flowsheet. Recently, flowsheet changes made for neptunium recovery and replacements of certain critical equipment items have altered the plant`s capacity. The status of the plant is discussed in the Continuity of Operations, Plant Improvement Program, Reference 1; wherein, the need for expansion to a capacity factor of 4.0 by January 1, 1962, was envisioned. Reference 2 was prepared to implement that program. A new chemical flowsheet, Reference 3, was prepared to serve as a basis for the Purex Expansion Program. The purpose of this engineering study was to determine the changes and capital expenditure needed to obtain a 33-1/3 T/day instantaneous production rate through the Purex Plant. This report discusses equipment additions and modifications that are required for the Purex Plant to operate at an instantaneous rate of 33-1/3 tons of uranium per day on the flowsheet, as described in Reference 3.

The feasibility of contoured I&E cans for production use has been demonstrated using our present flat base I&E sleeve (HW-37187). Studies by Process Engineering and Quality Control have shown that only a material savings would result from the use of only the contoured I&E can. Consideration was then given to the use of contoured sleeves (H-3-16879) to improve the contact areas and the resulting heat transfer during fuel assembly.