Reduced process water treatment costs and incidental benefits of smaller hexavalent chromium discharge to the Columbia River provided incentives to conduct a half-reactor production test. The sodium dichromate (Na{sub 2} Cr{sub 2} O{sub 7}2H{sub 2}O) concentration in process water supplied to the far side of 105-C was lowered from a nominal value of 1.8 to 1.0 parts per million (ppM). This test was started September 26, 1960 and is still in progress. However, a sufficient amount of data is available now to permit an interim evaluation of the corrosion effects noted as a result of the change inhibitor concentration.

The purpose of this test is to obtain data concerning the reactivity effect of horizontal control rods in the E-N loading at H Reactor. The accurate calibration of the control rods will then provide more accurate measurement of the other reactivity variables associated with the E-N loading.

The objective of the test was to evaluate the behavior during irradiation of nominally 1.739 inch OD, 1.074 inch ID, Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. The test elements were fabricated with the Be-Zr alloy brazed end closure planned for use on N Reactor fuel elements. Iron supports were used to minimize process tube scratching during charge-discharge.

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One of the characteristics of the safety control system of the Hanford reactors which is of primary concern from the standpoint of reactor safety is the response time. The purpose of this study is to determine whether the safety control system is sufficiently fast-acting to prevent an intolerably large power excursion from developing. An intolerably large power excursion is one that would cause a melting of the uranium while the reactor power is above the previous operating level. The purpose of this report is to show the techniques used to analyze the speed of control of the Hanford reactors. This report will help to standardize the methods and reduce to a routine the solution of this type of problem. The analog circuits will be presented and explained. A report has been written previously on the speed of control. The changes in the problem have necessitated the redesigning of the analog circuit and also the issuing of this report. This report compiles and organizes the analog work done on the speed of control to date.

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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.

The Expansion Joint Test are detailed in this report are part of the work accomplished under Design, Development and Research Contract DDR-111 between General Electric Company, Hanford Atomic Products Operation and Washington State University. The equipment and instrumentation used for the K-Downcomer tests were arranged to permit installation and testing of the expansion joints.

Current NPR fuel production plans call for a thick layer (0.030 inch or greater) of 5% Be + 95% Zry-2 braze alloy in the closure region. This requirement was imposed to eliminate many of the production welding problems brought about by the presence of the low melting braze alloy between two surfaces of Zircaloy. All GEH-4 irradiations in the past have involved very thin braze lines (0.015 inch or less). As a part of the fuel evaluation program it is essential to run a comparative irradiation to determine what effect the braze line thickness has on the stability of the fuel closure. For this purpose three fuel elements were prepared, two with a braze thickness of 0.030 inch and one with a braze thickness of 0.015 inch. To provide a more severe thermal stress, the I&E geometry was used. Five MTR cycles should be sufficient to test this fuel concept. This report details this test proposal.

Output of fuel elements during May was 107% of forecast. Engineering of present reactor fuels and N-Reactor fuel development are discussed. (DLC)

This test authorizes installation of up to ten non-overbore size zirconium smooth-bore process tubes into KW Reactor and continued charging of these tubes with KVNS fuel elements until authorized by other means (Process Standards or PITA) or until this test is terminated. While the test authorizes up to 10 tubes, only two process tubes are immediately available and are all that will be planned for in the initial installation and charging. Goal exposure will be set at 800 MWD/T.

This report details model studies performed as required by the design, development, and research contract between the General Electric Company and Washington State University. These studies provide analytical considerations for K-Downcomer and Bellows.

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The KSE-3 element, a 1.6% enriched Zr-2 Jacketed tubular element nominally 1.74 inch O.D. by 1.05 inch I.D., was designed for irradiation in the KER loops to simulate the behavior of an N-reactor outer fuel tube. Three charges of these fuel elements have been irradiated under PT-IP-363-A: one in KER-2 to 1985 MWD/T, one KER-3 to 3555 MWD/T, and one in KER-4 to 1.195 MWD/T. This document provides the calculated powers and temperatures for each fuel element during the time it was irradiated.

A product specification will impose operating problems for the HAPO reactors and the separation facilities. A preliminary analysis of several methods of operating have been considered using a linear program analysis. This document considers some of the implications. A linear programmed study of HAPO reactors was made in which six percent Pu was maximized under several reactor plans.

The monthly report for the Hanford Laboratories Operation, May 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, operations research and synthesis operation, programming, laboratory auxiliaries operation, and professional placement and relations practices are discussed.

The objective of this supplement is to review the basis, justification and procedure so that this production test may be used permitting a determination of minimum downtime, when advisable for improving moderator coefficient data as function of exposure.

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This report consists of eight curves, showing Plutonium-240 concentration and conversion ratio as a function of graphite temperature for various goal exposures. A range of 450 to 1000 degrees centigrade on the moderator temperature is used. Other parameters are consistent with the methods and constants used in present product accountability. No attempt has been made to state absolute conversion ratios or Pu-240 percentages. The purpose of this report is to provide a basis for use in economic studies involving changes in graphite temperatures. No conclusions as to operating changes should be inferred from these curves since the combined economics of any change in graphite temperatures include significant and complex factors in addition to conversion ratio and product quality consideration.

Fuel Fabrication and Evaluation. Nearly stoichiometric, low nitrogen- content UC was synthesized in the plutonium glove box atmosphere. PuC and PuC- UC preparation studies were initiated by the oxide-carbon reaction. UC with nickel additions lowered required sintering temperatures, improved density over control straight UC samples, but did not improve densities over those obtained previously with UC. Microprobe analysis of niobium and 21/4 Cr- 1 Mo compatibility samples tested 4,000 hr at 820 deg C, showed no uranium penetration. Irradiation Test. The W1-1 capsule containing two clad UC specimens continued operation to 11,000 MW-d/ton by the end of April. The W1-2 capsule was inserted in WTR, but had to be removed after a short time because of a radioactive gas leak. Plutonium Facilities. The facility at The Carborundum Company started operation with plutonium in March. Modifications and maintenance continue to be required and are being completed with minimum effect on experimental work schedules. The major modifications of the facility at NDA, the once-through nitrogen and helium systems, were completed and initial operation is satisfactory. A performance test was initiated prior to operations with plutonium. Design and construction of equipment for the furnace box are in progress. (auth)

For the purpose of evaluating the compatibility of graphite and INOR-8 in a dynamic fluoride fuel medium, INOR-8 Forced Convection Loop No. 9354-5 was operated 8850 hr. The loop operated at maximum temperature of 1300 deg F and circulated a fluoride fuel of the system LiF--BeF/sub 2/-- UF/sub 4/. Post-test examinations of the graphite and loop components revealed no apparent corrosion or carburization problems. (auth)

Activities in a program to obtain UC pellets of maximum density for irradiation testing are described. A study was made of the effects of the UC powder thermal history, sintering time, sintering temperature, and additives on the UC sinterability. Preliminary results indicate that the UC powder synthesized under the most severe conditions of temperature and time (1740 deg C, 107 min) was less sinterable than powders prepared at lower temperatures, or at the same temperature for shorter time. It was also concluded that although both temperature and time of sintering pellets affect density, temperature is more important. Additions of Fe (0.1 to 1.0%) improve sinterability and promote grain growth. The final density obtained on sintering in a vacuum was about the same as that resulting from sintering in He at atmospheric pressure. (J.R.D.)

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