The PRTR is entering a phase of operation in which there is an increased danger of high level fission product release from failed fuel. The higher fuel operating temperatures result in a much larger percentage fission gas release from the fuel crystal; also it is believed that the central voids and inter-crystal cracks greatly improve the transport of fission gases from the far end of a fuel rod to a defect location. 6 tabs.

This report, for June 1965 from the chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

This report for December 1964, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and weapons manufacturing operation.

This Hanford Report to the Working Committee details activities and research programs in current reactor production fuels, N-Reactor fuels, N-Reactor fuel development, and current reactor fuel development.

It is planned to manufacture ceramic target elements for use in N-Reactor. The potential exists for overdilution of the lithium-aluminate with aluminum powder. One method of nondestructively determining the target element type is by neutron absorption. This technique makes use of the different thermal neutron cross sections of aluminum and lithium. The target element to be tested is placed between a neutron counter and a neutron source--the neutron count with the unknown sample is then compared with that of a standard. An experiment was conducted to determine if a neutron absorption instrument could be used to identify a lithium or aluminum target element. A sketch of the test arrangement is shown. Test results are presented.

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Declassified 28 Aug 1973. Emphasis was given to the use of tungsten- clad uranium dioxide particles instead of surface cladding to reduce fuel loss during the fabrication and the high-temperature operation of tungsten-uranium dioxide reactor fuel elements. Two fabrication methods were investigated. ln one method individual unsintered hexagonal tubes were stacked, isostatically pressed, and sintered. The other method formed the entire unsintered honeycomb as a untt which was then sintered. Current emphasis is directed toward the latter method which eliminates problems of tube joining and inspection. Results of initial tests of equipment for direct forming of a 163-channel honeycomb with uniform fuel loading are described. (39 figures, 16 tables) (auth)

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This report, from the Chemical Processing Department at HAPO, August 1965, discusses the following: Production Operation; Purex and Redox Operation; Finished Products Operation; Maintenance; Financial Operations; facilities engineering; research; and employee Relations.

This report, from the Chemical Processing Department at HAPO, April, 1965 discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance;Financial operations; facilities engineering; research; and employee relations.

This review reports progress made in implementing the Purex Measurements Quality Control Program and findings of the initial statistical review of data obtained on the four major transfer stations. The four transfer stations are the primary product streams, as measured through K6 Tank and the PR system, and the two principal waste streams, as measured through the D2 and F15 Tanks. Uranium feed input to Purex through Tank D5 was measured starting with the first charges of CY-1965; comparisons with IPD statements have been developed. Measurements Quality Control Data are being generated on four other Purex waste streams, and statements concerning these will appear in subsequent reports.

This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

The cited paper presents data which establishes the equilibrium temperature for the alpha-beta transformation of Pu at 117.0 ±0.5°C. This was observed by following the electrical resistance change in thin, high purity, mixed-phase specimens as they were thermally cycled near the transformation temperature. As expected the time required for small phase changes near the equilibrium temperature was long. Data regarding the mechanisms of the alpha-beta and beta-alpha transformations or rates as a function of temperature were not presented.

This report discusses measurements of the radiation levels in the Centaur stemming materials which were made 260 ft. and 360 ft. from the device and at the surface 560 ft. from the device. The measurements were made in the fill in the casing. The radiation levels are provided. the material reaching the counters is fractionated due to its filtering through the fill. It can be assumed that the major components are the rare gases with perhaps some contribution from the halogens. The decay rate of the gases is similar to that of mixed fission products to within better than a factor of 1.5 out to a decay time of about 10 days. For halogens the factor is about 2. Thus in analyzing the readings the error is not large if the mixed fission product decay rate is used. The assumption is also made that the activity is due to the density or pressure of gas and not to local deposits of fission products at or near the position of the counters.

Report about the.Additional radiation and shielding experiments needed at WANEF.