The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)

This is the third quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.

This report, for February 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Financial operations; facilities engineering; research; and employee relations. Weapons manufacturing operation; and safety and security.

It is necessary to modify existing I&E fuel element components to produce the requested target elements by early April 1963. Normally, a minimum of eighteen weeks is required to produce components of a new design. Therefore, the finished target elements will not be of the optimum designed dimensions. The proposed minor deviations have been approved by Reactor Engineering for the demonstration load. It is anticipated that only these test quantities will be fabricated to these dimensions. These provisional process specifications are established on this basis and are subject to change as the fabrication techniques are developed.

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Data are summarized on levels of radioactivity in environmental samples collected at Hanford during 1966, including detailed data on samples collected during December. Data are included on the radioactivity in fallout from Chinese and Russian nuclear weapons test, samples of drinking water and Columbia River water, the /sup 56/Mn content of Columbia River water sampled at various locations, the /sup 131/I content of gaseous wastes and surface waters, and the radioactivity of soil samples from the chemical separations liquid waste treatment and disposal area. The radiation dose to personnel during the year from all enviromnentl sources was estimated to be less than 0.3 percent of the applicable limits. (CH)

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Tests were made on butterfly vaives similar to those used in the discharge leg of each of the three external recirculation loops of the Pathfinder reactor in order to determine the critical values of a dimensionless cavitation number ( /occurred in pu ) used to specify the limits of operation for reactor valves, at incipient cavitation. The experimentally determined values of the cavitation number were used to determine the cavitation-free control range of the Pathfinder valves. The tests showed that both the undissolved and dissolved air content of the water caused cavitation to occur at higher values of sigma. It appeared that cavitation first occurred in the vortices downstream of the valve disk. A limiting cavitation condition was defined for the reactor butterfly valves. (M.C.G.)

Statements are presented concerning project objectives, major accomplishments in FY 1962, progress during the report period, evaluation of effort to date, and next report period activities. The subject material covers reactor separation and fuel element ejection, reactor transient and excursion tests, reactor end-of-life shutdown devices, fission product release studies, critical configuration tests, mechanical and thermochemical effects, and fuel element burnup and fission products dispersal. Major emphasis for the period was concentrated on the design of the SNAPTRAN 2/10A-1 and -2 machines and the models for the Reentry Flight Demonstration (RFD-1). Planning of the SNAPTRAN experimental program was undertaken. Analytical effort was concentrated on developing the several computer codes required for interpreting and understanding the data acquired or to be acquired from the experiments. The majority of the Phase I mechanical and thermochemical effects test program was completed. A few fission product releases were conducted at the NRTS. Necessary test apparatus for the water immersion critical experiment was designed and fabricated. (auth)

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Declassified 5 Sep 1973. Information is presented concerning LCRE specifications, reactor kinetics, fuel elements, primary coolant circuit, secondary coolant circuit, materials development, and fabrication; and SNAP50-DR- 1 specifications, primary pump, and materials development. (DCC)

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A test was run to determine the capability of the nuclear instrumentation system to indicate reactor transient behavior and to test the linearity and alignment of all four channels. The response to a resctivity insertion was found to be linear in the range tested 5 x 10>s-/sup >> / 5 x 10>s-/ sup > /p Channel A showed the best aligmnent. (D. L.C.)

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A mass flow measurement technique was devised which meets many requirements for mass flow measurement systems. In this technique. fluid is made to pass through a pivoted S-shaped tube. which tends to rotate due to the angular momentum of the fluid. A torque motor and torsion spring maintain zero displacement. the restoring force being a measure of the angular momentum, and density is measured by absorption of radiation passing through a window in the S tube. From the measured angular momentum and density, the mass flow can be computed. Two experimental mass gages using this technique have been constructed. (D.L.C.)

Several coating techniques were studied with the objective of protecting beryllium neutron reflectors from oxidation during long-time grounnd testing of a SNAP-8 experimental reactor. The techniques include enameling, metallic slurry coating, and pack-cementation conversion coating. In addition, several commercial coatings for beryllium were evaluated. Based on screening and comparative oxidation evaluation studies an anodic coating was selected as being capable of affording the necessary protection. (auth)

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The problem of making measurements of restricted spaces is presented and eddy-current techniques are proposed as a possible solution. Theory is presented. The design philosophy of test probes is discussed. Several probe styles are described and their application to inspection problems is shown. (auth)

From introduction: "Evaluations to determine cause of fuel rods breakage following irradiation."

A variable-length vacuum-insulated liquid hydrogen transfer line is described. The vacuum system is semi-permanent, and segments of the line are assembled with only threaded vacuum fittings. Thermal stress calculations are presented for a statically indeterminate union coupling.