From introductory paragraph: "The study of the counting techniques of gamma-emitting radioisotopes is of a great deal of interest to workers in the field of radiochemistry. Of particular interest to the long-lived gamma emitting isotope of yttrium which is commonly prepared by a deuteron bombardment of strontium and is reported to decay by K-capture. This isotope, which is of interest in the fields of biochemistry and metallurgy was tentatively assigned to mass 86. Since a 2.0 hour activity was observed from a neutron irradiation of yttrium, the assignment was considered fixed. Subsequent work indicated a possibility of a long-lived gamma emitting activity arising in the fast neutron irradiation of yttrium. The published data did not agree with theoretical calculations as to the possibility of these two activities being isomers. This work was undertaken to study the characteristics of the radiations from the isotopes; to have data available on the long-lived activity; and, to attempt to fix the mass assignment."

Discussing a geological reconnaissance of the King Tut Mesa, East Carrizo District.

Structural map of the King Tutt Mesa, East Carrizo District, in New Mexico produced for the U.S. Atomic Energy Commission's mining operations. Scale 1:24,000

An addendum to report HW-30390 a additional power generation calculation for P, the rate of energy release, in kilowatts, was derived.

Abstract: "A particularly conventional modified form of Maxwell distribution is chosen. The modified expressions for (a) the energy transfer from the ions to the electrons in a plasma and (b) the brehmestrahlung from the electrons are calculated. Using the expressions some possible steady-state conditions for the ion and electron gases are derived and compared with those for the usual Maxwell distributions."

A report discussing a geologic reconnaissance of a section of the Kaiparowits Plateau region of Utah was conducted to evaluate the uranium potential of the area.

Report discussing the survey work done at the Battelle Memorial Institute with the objective to successfully build a gas-cooled reactor.

Report discussing a study to obtain a quantitative measurement of the movement and distribution of hydrogen among components such as magnesium metal chips, uranium tetrafluoride, and magnesium fluoride slag, similar to what would occur during a reaction in a thermite bomb.

"A number of mixtures of polymers and multi-unsaturated monomers have been prepared and irradiated. The content of insoluble gel of irradiated samples of these polymer-monomer mixtures has been determined by extraction."

Report issued by Oak Ridge National Laboratory that describes research and progress at the Chemical Technology Division.

The Heavy Water Components Test Reactor (HWCTR) is used to test prototype fuel elements for power reactors that are moderated with heavy water and fueled with natural or slightly enriched uranium. During the initial critical experiments in the HWCTR, it was observed that there were unexpected variations in nuclear reactivity. Investigations revealed that this effect was due to bubble of helium gas appearing and disappearing in the moderator. An examination of the expected operating conditions of the HWCTR and the solubility of helium in D2O showed that it was possible during normal operation for the helium content of the moderator to exceed saturation and thus for helium to appear as bubbles in the moderator. The possibility of helium bubbles appearing in the moderator because of solubility characteristics was eliminated by modifications to the process system so as to maintain the gas content of the moderator appreciably below saturation.

The Heavy Water Components Test Reactor (HWCTR) is a pressurized reactor, cooled and moderated with D2O, and has the capability of testing fuel assemblies under operating conditions of coolant flow, temperate, and pressure that are typical of those proposed for modern power reactors. The report contains (1) description of the four systems used for failed element detection, (2) discussion of the laboratory analyses of water samples used a as backup for the fuel failure instruments, (3) description of 3 monitors, Cyclic Air Sampling Monitor, Stack Gas Activity Monitor, Health Physics Building Monitors, (4) normal full power activity readings, (5) discussion of the experience during fuel failure.

Summary: Two UO2-filled stainless steel clad fuel rods in which fission gas pressure was measured during irradiation have been subjected to post irradiation examination. Results of free gas analysis and metallographic examination are in general agreement with observed pressures reported previously. Calculated fuel surface temperatures based on extent of fuel recrystallization indicate that in a one-half inch diameter fuel rod with 0.014 inch diametral clearance operated at a maximum heat flux of 531,000 Btu/hr-ft, gap conductance increased with increasing heat flux. An analysis of void configuration indicates that pressure is more sensitive to as-fabricated void volume and changes in this volume resulting from fuel expansion than to fuel central temperature. The decreases in effective void volume with increasing fuel temperatures becomes more significant as initial void volume decreases, and excessive fission gas pressures may be developed in fuel rods operated at high fuel temperatures unless adequate expansion volume is provided in fabrication.

The Heavy Water Components Test Reactor (HWCTR) was built for the Atomic Energy Commission by the Du Pont Company to satisfy a need for fuel testing in the AEC's Heavy Water Power Reactor Program. The reactor was designed to provide a realistic test environment for full size fuel candidates. The report contains sections on (1) the containment building, (2) vertical cross section of the reactor vessel, (3) core layout, (4) low power physics tests and comparison with calculations, (5) rod worths, (6) temperature coefficients, (7) flux shapes, and (8) the operating philosophy of a test reactor.