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A two dimensional photoelastic study of two designs of clamps for the Phoebus 2 main closure is detailed. Predicted prototype stress data is given in the form of a stress parameter which includes the axial load and a representative clamp radius.

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This report addresses a brief review of he international symposium held in Albuquerque, New Mexico.

This document provides Operating Limits which shall be applicable to the eight production reactor facilities, designated B, C, D, DR, F, H, KE and KW (hereinafter referred to as the Hanford Production Reactors) located at the Hanford site.

This report is about the Classical Dynamics of Triatomic Systems which is divided into three parts.

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In the bombardment of materials with heavy particles a large amount of energy can be deposited in a very small region by a primary knock-on atom and the local atomic arrangement can be thereby drastically disrupted. Various measurements of physical properties of such irradiated materials indicate the presence of distributions of defects which are removed in a step-like manner by annealing. One of the more interesting physical property changes accompanying fast particle irradiation is the attendant change in mechanical properties of irradiated crystals. The defect which is responsible for the mechanical property changes of irradiated crystals is only removed at high temperatures, temperatures coresponding to self diffusion. This observation, as well as others, has led to the model of a depleted zone as being responsible for the changes of mechanical properties of irradiated crystals. A depleted zone is envisioned as a region of crystal where a high local concentration of point defects exists - a belt of interstitials surrounding a multiply connected complex of vacancy clusters. We would like to present here some evidence which lends support to the existence of such defects.

Production Test IP-546-A. consisting of 20 charges for the purpose of irradiating the first hot die sized fuel elements was charged in C-Reactor July 27, 1963. A second tests PT-IP-616-A containing a total of 19 charges had been charged on two separate outages; 13 land 6 tubes on September 28, 1963 and October 30, 1963, respectively. Fabrication of test quantities was becoming more routine and additional irradiation tests were planned. This report summarizes the fabrication of hot die sized fuel elements originally intended for Production Test IP-630-A, but changed to ``Supplement ``A`` to Production Test IP-546-A, Irradiation of Diffusion Bonded Fuel Elements,`` HW-75465 E. The production test was changed due to unexpected growth behavior of hot die sized fuel during irradiation.

The oxidation of graphite in the Hanford reactors is of consequence since graphite burnout affects the strength of the moderator. As a means for indication of any highly oxidizing condition within the stack, containers or boats of small weighed samples of reactor-grade graphite are positioned along the length of an empty process channel in each reactor. The rate of oxidation of the monitoring samples, referred to as the burnout rate, is reported as percent weight lose per 1000 operating days (%/KOD). Currently the burnout rate limit is 2%/KOD. This document presents recent burnout data at the C-reactor.

Early in December 1963 eighteen natural uranium columns were discharged from C Reactor. Fifteen (15) of these columns contained alternately charged HDS (test) and AlSi (control) fuel elements in the downstream half (positions 1--16); two columns were charged full length with HDS material; and one column was charged full length with AlSi material. All canned pieces were nominally C5NS dimensions except that the HDS pieces were slightly longer than the standard AlSi pieces. Uranium fabrication history, through heat treatment, was controlled ad equivalent for both test (HDS) and control (AlSi) material. For these eighteen columns average exposure was {approximately}960 Mwd/ton, average tube power was {approximately}1125 kw, and average tube outlet temperature was {approximately}100 C. Two striped charges were discharged in September 1963 @ 370 Mwd/ton. This report presents results of the post-irradiation measurements that have been completed and analyzed as of this date. A second set of measurements for a portion of the material is being programmed.

Because of the unexpected growth behavior of hot die size fuel elements during irradiation, it was necessary to re-evaluate the plans for hot die size irradiation testing and redirect the development effort. Tests were initiated to determine the cause of the growth, and plans were made to incorporate findings into subsequent irradiation tests. This report summarizes work done to determine the cause of the unexpected growth and the status of irradiation tests designed to measure improvements in the growth behavior of irradiated hot die size fuel.

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During the 0000--0800 shift on August 21, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 2, 3 and 4 monitors indicating a possible fuel element failure in Loop 1. The KER Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant and coupon samples taken from Loop 1.

This report to the FEDC Working Committee details activities in N-Reactor fuel element fabrication and materials testing for the time period of September 1965 to January 1966.

Recent high tank drawdown data obtained at F reactor during periodic high velocity flushes indicated a reduction in flow to the reactor due to building of corrosion products in the high tank discharge lines. The apparent flow reduction at F reactor was verified by conducting a high tank drawdown test. Visual inspection of B, D, and F high tank discharge lines revealed comparable densities of corrosion product buildup, and high tank drawdown data during high velocity flushes at B and D also indicated a reduction in flow. High tank flow rate to the reactor under simulated emergency conditions needed to be accurately determined to establish current backup adequacy. This report presents the results of the tests which were conducted at D reactor on January 20, 1963 and at B reactor on February 11, 1963.

Reactor fuels, reactor engineering, radiological engineering, process technology, and operational physics progress is reported for irradiation and testing at the Hanford production reactors.

This monthly report details research and engineering operation activities of the Irradiation Processing Department for the month of September 1965.

This document provides the Hanford Production Reactors operating histories from January 1, 1961 through November 30, 1969. The raw log sheets are provided.

During the week of March 1, 1965, KW Reactor shut down with indications of a tube leak. Leak testing during the shutdown indicated a front Van Stone flange leak on tube 3065 and a suspect internal leak on tube 3075. During the tube removal process, there was indication of Zircaloy embrittlement on both tubes. Subsequent metallographic examination of samples taken from these tubes indicated the presence of case hydriding on the internal tube surface extending from approximately the end of the active fuel corn to the rear Van Stone flange. Vacuum analysis of selected samples revealed the total hydrogen concentration, including the hydrogen present in the hydrided layer, ranged from approximately 50 ppm at the end of the active charge location to approximately 1300 ppm at the rear Van Stone flange, Since examination of these first two Zircaloy tubes removed from KW Reactor, two additional tubes have been removed from KW Reactor, two tubes have been removed from KE Reactor, and one C-size Zircaloy tube has been removed from C Reactor. The presence of hydriding has been observed on the seven Zircaloy-2 tubes removed to date. It is the purpose of this document to review in some detail the data …

This report covers progress in the following areas: process and reactor development; process technology; operational physics; and testing. Process and reactor developments covers reactor fuels, reactor engineering and radiological engineering. Process technology includes process standards, process change authorizations, and process standard relaxation. Operational physics includes updates on the B, C, D, F, H, KE, and KW reactors along with summaries of studies on reactivity and control and production related studies. Testing includes plant assistance; IPD and testing and irradiation services; other departments and contractors.

The described information consists of fuel element specifications, irradiation system parameters, operating conditions, and failure observations to include rupture identification.

The objective of this production tests is to irradiate N Reactor prototype and candidate fuel components and alternate products at simulated N-Reactor pressure and temperature conditions in KER Loops 1, 2, 3, and 4.

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