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

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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.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the materials being irradiated, awaiting disposition and material shipped during the report period. The data are given in table form. Information consists of: TISR No.; request number; target material; piece number; operating time; CMK absorbed; charge date; location; exposure to date-NVT; discharge, date and time; and shipping date.

This document presents details about the status of irradiations performed by Fuel and Target Irradiation Technology for BNW as of November 30, 1969.

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. Data are given table form. An explanation of the various columns in the report is given.

To provide flow increases in excess of the current water plant capacities at the old reactors, a short-range water modification program has been proposed by Facilities Engineering Section. The proposed program outlined by Facilities Engineering Section includes increased 181 and 183 building pumping capacity at B, D, and H areas, a new filter for F area, and larger impellers for the 190 building pumps at H area. It has been estimated that beneficial use for this proposed increased water plant capability can be obtained by the late fall of calendar year 1962 if prompt project approval can be obtained. In order to obtain an economic benefit from the proposed water plant capacity increases, methods of increasing flow through the reactor must be devised. Initially, various publications discussing this project inferred that rear Parker fitting reaming and installation of larger diameter rear-face pigtails were the only methods by which reactor flow increases could be economically justified. Hence, initially, acceptance of the short-range modification program appeared dependent on Parker fitting reaming and larger rear-face pigtails. Since the possibility of these two modifications will require further investigation, it is desirable to briefly explore alternate methods for increasing reactor flow so that the acceptance …

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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.

A study was undertaken of means for rendering the plant less vulnerable to self-destruction with radioactive contamination spread. It was concluded that the only course of action was to totally discharge the reactors and provide water cooling flow by gravity to the reactor storage basins. This report reviews the technical considerations involved in determining the feasibility of the course of action with emphasis on assuring basin integrity.

A significant portion of the planned production.gain expected from the FY 60 Reactor Plant Improvement Program was directly related to overboring the existing graphite channels. The overbore contemplated was a modest 200 mil enlargement (which would not require enlarging the reactor shield penetrations) at those reactors which were the last to require tube replacement. This was all that appeared feasible in view of the developmental work which had been accomplished at the time the program was prepared. Recent studies have confirmed that large incentives exist for overboring the reactor process channels approximately 500 mils in the C and 5 old reactors. Conservative estimates of the incentives for overboring indicate a payout period of about two years for the proposed work based on an increase in plutonium production of 15--18% derived from increased conversion ratio, and a reduction in plant unit cost. The proposal to overbore the graphite channels approximately 500--550 mils in one or more of the present Hanford reactors will require fuel elements about 0.5 inch larger in diameter than the present I&E fuel elements. Since there is only limited experience at HAPO in fabrication and irradiation of large diameter fuel elements, parallel development of large fuel elements is …

The nuclear heat generation rate in the first capsule irradiated was higher by a factor of two than was calculated. The original capsule was irradiated in a dry bore with cooling water in the annulus only. The new capsule will be irradiated in a water-cooled bore facility with additional cooling coils around the lithium containing tube. This will keep the inner capsule temperature below 150 C during the initial tritium buildup period prior to outgassing. This Supplement authorizes the irradiation of an additional capsule and the removal of the present facility and installation of a single tube general purpose facility. All remaining provisions of the original development test are in force except for minor exceptions due to the water flow in the bore which have been changed in the following writeup.

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

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.

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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.

A significant reduction in non-equilibrium losses is possible through the use of poison splines for reactivity and heat distribution control during reactor startups. The curves presented show the results of an analysis of recent KE Reactor poison spline startup usage. These curves demonstrate the magnitude of gains possible at other reactors through the use of poison splines for turnaround control.

Alum is used as the coagulating agent in the water treatment process at Hanford. The bicarbonates present in Columbia River water react with the alum to form a loosely knit aluminum hydroxide molecule. Finely divided particulate matter and large organic molecules present in raw water are adsorbed by the floe particles. Partial is accomplished by settling in the basins; however, gravity filter beds remove the greater part of the suspension load. A polyacrylamide is added to the filter inlet stream to form a binding net around the floe particle. The floe particle is now more resistant to shearing and a greater amount of small particles are retained in the filter bed. The objective of this test was to re-capture parent isotopes of phosphorous and arsenic that had passed through the filters by secondary alum coagulation. The size and density of the floe particle would be increased by employing bentonite for the nucleus. The larger particles should now pass through the reactor with minimum residence time for activation. A polyacrylamide would again be used to net or toughen the floe particle.

In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless steel- and Zircaloy-2-clad fuel elements. During 1956 and 1957, stainless steel-clad elements were tested in the Materials Testing Reactor (MTR), Hanford H Reactor Loop, and the KE Reactor Recirculating (KER) Loops. During 1957, a coextrusion method for cladding uranium rods with Zircaloy-2 was developed. The first irradiation of Zircaloy-2-clad fuel from an off-site supplier began in late 1958. The objective of the irradiation was to study the dimensional stability of the fuel rods and a seven-rod fuel assembly. Two coextruded, seven-rod elements were irradiated in KER Loop l.

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 …

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

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.