The Quality Plan for the SNAP-27 Follow-On Program describes the manner in which the Isotope Power Systems Operation of the General Electric Space Division will control product quality. NASA NHB5300.4 (1B) and AEC QASL-SNAP-1 and 2 have been used as guides in the development of this plan and, upon approval by the AEC, this plan will serve as a policy document to be utilized in implementing the SNAP-27 Follow-On Quality Program.

In order to build a thin particle detector with 10 micron spatial resolution and automatic readout, the avalanche of ionization electrons in high electric fields in liquid argon and liquid xenon has been studied. We present a scheme using an array of points that could be used to make a reliable liquid argon filled detector. The avalanche pulses in liquid xenon have a rise time more than three orders of magnitude faster than that in liquid argon, suggesting that the positive charge carriers are holes, and making possible a detector with a time resolution of better than 100 nanoseconds. A direct observation of hole conduction is described.

This final report details production test-176, the primary purpose of which was to provide a quantitative comparison of fuel element 8001 aluminum alloy cladding corrosion in cooling water containing 0.5 and 1.0 ppm sodium dichromate inhibitor. Secondary purposes were to provide information on cladding corrosion as a function of temperature and as a function of time at both inhibitor concentrations. The primary purpose was well fulfilled: Equations were developed to describe and predict fuel element weight losses at both dichromate concentrations and the effect of dichromate concentration on localized corrosion was clearly established. Little effect of dichromate concentration on localized corrosion was observed when fuel cladding temperatures were below 115--120 C but above these temperatures the localized corrosion definitely was more severe in coolant containing 0.5 ppm inhibitor. The bottom rows of fuel element supports rapidly corroded away at the higher temperatures which caused a further increase in local temperatures due to flow imbalances and this in turn accelerated the localized corrosion. Because the higher dichromate concentration reduced the amount of support corrosion, 1.0 ppm dichromate should be employed to control localized corrosion whenever cladding temperatures are expected to be above 120 C for long periods of time. These tests …

In this semiannual issue the single pass reactor and water plant data are shown for the six-month period January through June, 1970, together with data for the three preceding six-month periods.

This report presents a review of current 100-K Plant liquid waste disposal practices. The report s divided into two sections with Section I consisting of a general description of the Plant facilities to dispose of liquid wastes by ground disposal or by direct discharge to the Columbia River. Section II further appraises liquid waste disposal practices by examining each material that is used in any significant degree in Plant operations. For ease of presentation in Section II, the materials are grouped into general categories of usage with two primary considerations reviewed for each material, i.e., (a) the storage and supply arrangement with emphasis on provisions or safeguards to prevent accidental discharge and (b) the specific application of the material in the process, manner of usage, and final disposition. The report should be viewed as only an informal source of data to aid in the future preparation (by others) of a comprehensive environmental control plan document. Suggestions as to refinements, additions, or corrections are solicited.

None

None

None

The cyclic corrosion resistance capability of an R-1 type periphery featuring a multiple layer Z-liner thermalized rerolled pyrofoil wrapper was experimentally measured. This test employed an SX-5 graphite core and simulated fuel elements.

None

None

None

None

None

The geology and hydrology of the Hanford Reservation are reviewed, with emphasis on ground water flow, to identify those areas that should be restricted from unconditional release due to radionuclide cortamination or radioactive waste storage as well as those areas that would have no hydrological restrictions. The effects of the discharge of large quantities of cooling water from the radiochemical plants on ground water flow were also evaluated. (CH)

None

None

None

None

None

Two 90UC--10ZrC fueled converters, IC-13 of Mark VI configuration and IC- C3 of Mark VIIB configuration, were examined in hot cell after in-pile operation. IC-3 operated for 4395 hours at an average emitter temperature of 1675 deg C as a converter test and then for 2945 hours at an average emitter temperature of ~1500 deg C as a fuel irradiation test; the average fuel burnup achieved was 2.5 x 10/ sup 20/ fission/c.c. IC-C3 operated 5445 hours at an average emitter temperature of 1670 deg C as a converter test; the average fuel burnup achieved was 5 x 10/ sup 19/ fission/c.c. The carbide fuel contained 4 wt % tungsten and had a C/U atom ratio of 1.05. Other unique features for the converter components were fluoride tungsten claddings of controlled fluorine contents (18 ppM for IC-I3 and 19 ppM for IC-C3), and the presence of a high temperature seal and a graphite sorption cesium reservoir in IC-C3 converter. The results obtained on fuel swelling, emitter deformation, fuel-cladding interaction and microstructures of various converter components are presented. Solutions to the problem areas encountered are recommended. (auth)

None

None

None