In recent months, several process tubes installed during 1961 have been removed and examined out-of-pile in connection with Tube Corrosion Monitor Studies.1 Most of the tubes were believed to be uniform-wall .080in.-nominal-rib-height tubes. The ex-reactor dimensional measurements obtained near the inlet flange showed,that the tubes did not have uniform walls or .08011 nominal rib heights. Subsequently, dimensional measurements were obtained on approximately 200 new process tubes in an effort to determine the extent of dimensional variations in new process tubes as received from the vendors. The effects of the variations on tube corrosion and tube life are discussed in this report.

A research and development project for study of the effects of reactor effluent on Columbia River water quality is being sponsored by the AEC Division of Production. Work was started in October 1962, the first effort being aimed at furnishing an immediate answer to a security question: how closely can Hanford production be estimated by measurement of river temperatures? An interim progress report gave the results of the preliminary investigation. During the calendar year 1963, the study was expanded to meet broader program objectives. This document is a progress report for the year, covering the temperature and effluent distribution phases of the program. Progress on the chemical characteristics phase of the program is documented separately. Figure 1 shows the section of the river under study.

The fuel element for the test described in this report has been designed to extend the total exposure capability of metallic uranium fuel by altering the type of cladding deformations produced by uranium swelling. In a tabular fuel element of cylindrical geometry, irradiation-induced uranium swelling can cause splitting of the outer clad or buckling of the inner clad. With a fluted outer surface on a cylindrical element, a large amount of swelling may be accommodated by bending of the exterior cladding without the tensile strains which produce localized necking and failure. In addition, the fluted shape, by reducing the restraint on the fuel may direct the volume increases to the outer surface and decrease the likelihood of inner buckling. For this test, the fluted surface concept has been adapted to a tubular element that nominally fulfills the requirements for N-reactor fuel. It is desired to observe the performance of an element with this geometry at an exposure that will produce about 5 percent swelling. It is requested., therefore, that GEH 10-67 and GEH 10-68 be irradiated to an exposure of about 3000 MWD/T in the 6{times}6 M-3 Loop of the ETR.

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether purchase of refrigerators, ranges, sinks, a combination of the three percolators, cups, and the like need statutory pre-existing law to be paid out of funds in the State Treasury 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, Crawford Martin, regarding a legal question submitted for clarification: Penalty for operating a motor vehicle for the transportation of school children without signs on the vehicle containing the words "school bus".

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, Waggoner Carr, regarding a legal question submitted for clarification: Whether a check department established by the sheriff and operated in the manner outlined is a legal permissive operation.

We are pleased to enclose copies of our Work Statement and Cost Estimate as a subproject to your program to nondestructively inspect the fuels on your NASA-Lewis contract. This confirms our telephone call and teletype of November 19, 1965 from Mr. Chockie to you. As we understand, the duration of this agreement should extend over the next six or nine months and will probably include the inspection of one or two fuel elements singly; later on, three batches of five elements. Accordingly, we recommend that the program be established for a period of nine (9) months with an appropriation of $10,430, including the fixed fee of $660. The attached Estimated Costs sheets show estimated costs for inspection of one fuel element at one time and five fuel elements are one time. This estimate is on a CPFF best effort basis calling for the application of tests developed on our present NASA-Lewis program. No additional development costs are included in this program. Shipping of fuel elements between Columbus and Northwest to be prepared by Columbus.

The purpose of this supplement is to authorize charging the complete central zone core of H Reactor with the modified E-N charge makeup, installed as a 102-tube ``test core`` in the fifth loading. The potential economic and efficiency gains of a simplified charge pattern (a smaller average number of N pieces per tube and a minimum number of different charge types) were discussed in Supplement II to the parent PITA. Accordingly, a test block, consisting of 102 process channels in the center of the reactor, was included in the charging of the present (fifth) E-N core loading for the purpose of evaluation. Based on satisfactory preliminary confirmations of the calculated reactivity, front-to-rear flux distribution and other operating characteristics, extension to a full-scale core loading appears feasible. All resulting changes in pile reactivity and other operating variables will be minor and easily adjustable without significantly affecting operating efficiencies.

The purpose of this report is to describe, in a very brief and general way, some of these provisions and the role they play in consumer protection where public health and safety are involved.

This document is submitted in response to a request from the Atomic Energy Commission for a report on the safety aspects of reactor operation at bulk outlet temperatures in the neighborhood of 95 C. To properly describe the safety aspects of operation it is necessary to address the report to the engineering parameters associated with reactor operation and compare them to actual technical limits. Also, some discussion of administrative power level limits and bulk outlet temperature is in order.

This report summarizes the results obtained in the experimental measurement of the reactor heat extracted by the coolant during two different scrams of the DR Reactor. These tests were conducted with the reactor flow carefully controlled to establish different reactor coolant temperatures following the scram. During normal reactor scrams, which have been used in the past to measure the reactor heat output, a high coolant flow was maintained. Consequently, the coolant outlet temperature dropped very quickly from an operating value of 90 to 95 C down to 20 to 30 C following the scram. Under emergency conditions, however, with only the last ditch emergency flow available, the coolant outlet temperature could remain as high as 80 to 90 C. This condition could prevail because of the small amount of last ditch flow available, and could last for 5 to as long as 70 minutes after the reactor scram.

None

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.