"In the following report, a new technology is discussed which was first proposed in 1959, but which has been developed mainly since 1964; the in situ production of oil from shale by large underground retorts created by nuclear explosives. The first part of the present report describes this new process; the second part gives an analysis of the United States and the world endowments with crude oil resources and oil shale deposits and finally, the third part deals with expected cost estimates of this new technology as compared with present crude oil prices and potential costs of conventional shale oil production."

The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.

Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1965-66 fiscal year.

From abstract: The development, acceptance, and qualification tests performed on the SNAP-10A Ejectable Heat Shield and components, the results of those tests, and the conclusions drawn from the results are presented in this report.

Abstract: Pressure stress-rupture specimens of thin walled Type 304 stainless steel tubing have been tested at temperatures to 1300°F in the presence of an internal diffusion limited carbon source.

From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.

From introduction: This report details the extensive modifications to the SRE heat transfer systems required to accomplish increased capacity objectives.

From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.

Results of a questionnaire survey are presented on reactor supervisor and operator education, experience, and training, and on certification procedures by reactor category. The questionnaires were obtained from 362 supervisors, 393 operators, 44 supervisor trainees, and 139 operator trainees.

Abstract: This report presents steam cycle optimization studies for large sodium graphite nuclear power generating stations.

Abstract: Pressure-temperature isochores were obtained for zirconium-hydrogen alloys, spanning the H/Zr composition range of 1.430 to 1.910. The studies were confined to the temperature limits of 300 to 900ºC, and the pressure limits of 0.01 to 10.0 atm.

Final report on research and development on fabrication of pin and lid detectors and the dry run interface system.

Investigation of whether the multi-thousand psi pressure pulses that occurred in the BORAX-I and SPERT-I destructive power excursion could have been generated by thermal mechanisms in the geometries of unmolten reactor cores. These pressure pulses were "at least as high as 6,000 psi, and probably higher than 10,000 psi " in BORAX I, and "between 3,000 and 4,000 lb/in" in SPERT I. An experimental investigation was undertaken of pressure pulse generation by purely thermal means.

Abstract. the direct and inert-gas radiolysis, as well as the vacuum ultra-violet photolysis of CD3CH2CD3, CH3CD2CH3 and C3H2+C3D3 mixtures have been investigated in the presence of radical scavengers. The major conclusions are : (a) at atmospheric pressures, neutral propane decomposition contributes to the observed products although to a lesser extent than parent ion decompositions ; (b) a variation in pressure has a pronounced effect on the fragmentation of the parent ion ; (c) the hydrogen atoms in the ethyl ion are randomized in the direct as well as in the inert-gas sensitized radiolysis ; (d) rearrangement in the parent ion is of minor importance in the radiolysis ; (e) although the formation of propylene is related to the propyl ion, it is not necessarily produced by the neutralization of this ion.

This technical report describes the development, design, operation, and performance of a full-circle, radial-vane steam separator for the boiling water section of a nuclear superheat reactor. Steam-water tests of this model have demonstrated that is has vane capacity in excess of that required for the 300-Mx(e) separate superheat reactor and for the 300-Mw mixed spectrum superheat reactor. It is proposed that the vane capacity requirement of the 600 Mw(e) separate superheat reactor may be attained by increasing the nozzle length.

Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.

Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).

"lsotope dilution techniques are described for the assay of chlorinated hydrocarbon pesticides and organic phosphorus pesticides in foods. Results are given for the determination of tetranitro-DDT-dianilide, dianilide of tetranitro- DDE, dieldrin, systox, and derivatives of these compounds. "

From introduction: This report covers the results of a study of a mobile irradiator for fruit grown in California.

From abstract: "In this paper the motion of a nucleus with an intrinsic quadrupole moment in an external electrostatic field gradient is discussed from a classical point of view. It is shown that in the classical approximation the angular momentum may precess about the direction of strongest field gradient or about the direction of intermediate field gradient, but not about the direction of weakest field gradient. The classical precession frequencies are found to be related to the quantum mechanical dipole transition frequencies."

From introduction: The purpose of this survey was to document the pre-event and post-event condition of all existing surface facilities within a 10-mile radius of ground zero for Project GNOME.

Abstract: This technical report contains a summary of experimental and analytical work performed on cold clean SM-1 Core II with special components and PM-2A Core I each with thermal shield and vessel mockups. The purpose of this work was to define the neutron intensity and spectra to which the pressure vessels are subjected in order to assess the effect of irradiation on the vessel lifetimes. The radial distributions of the energy dependent neutron flux per unit power in the core and vessel mockups are presented. The uncertainties associated with the measurements are also given. In addition to graphical and tabular presentations of the test results, discussions are provided on the experimental techniques and theory. A review of the analytical models is provided in addition to the calculational results. A special analytical study of the the PM-2A Core I power distribution and absolute power level determination is given. A comparison of the experimental and analytical results is made and conclusions and recommendations presented.

Abstract: A detailed description of the PM-2A reactor, primary system and instrumentation is presented. A general description of the secondary system and plant arrangement at Camp Century, Greenland is included. The results of the startup physics, shielding, thermal and hydraulics and radiochemistry test are presented. the analysis performed on the shielding and thermal and hydraulic tests is included. The shielding problem at startup and the shielding modification made to the plant are described along with the radiation measurements made in these areas.

Final design for the 30 megawatt intermediate heat exchanger and steam generator.