Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

From Review of Theory: " In practice, a very close approximation to the molecular orbitals can be obtained in this way. Recent calculations of this type, utilizing analysis and computer programs developed by the author, have resulted in the determination of the molecular orbitals for a large number of diatomic molecules in the form of Eq. (2). These functions, which are thought to be very close to the Hartree-Fock (i.e., the molecular orbitals demanded by theory) result, were used in the pictorial calculations presented in this report."

From Introduction: "The investigation of solar distillation described in this Summary Report is part of the wide-ranging program of the Office of Saline Water to develop economical processes for the conversion of saline water to fresh water." From Summary: " Since the submission of the Summary Report which covered the first two years' progress, several new stills have been constructed, including four basin-type stills for the evaluation of basin liners and other materials."

Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.

Report that "compares gas turbines with steam turbines as means of producing electric power from gas-cooled reactors with all-ceramic fuel elements." (p. 1)

This report details activities at Battelle Pacific Northwest Laboratory for the month of June 1965.

The objective of this supplement is to authorize recharging of the thoria in the fringe zones of the B, C, D, KE, and KW Reactors. Initial charging is described in the parent document. This authorization will serve as an interim measure until Reactor Process Standards have been approved to authorize fringe blanket thoria irradiations.

This report defines the plan and purpose for the Palanquin post-shot exploration program. This program is necessary to obtain data that is needed in the understanding of the Palanquin experiment, and related explosion phenomena, which can be obtained in no other way.

Another interesting application of nuclear excavation would be a sea- level canal 160 miles long across Israel, connecting the Mediterranean with the Gulf of Aqaba (and thus the Red Sea and the Indian Ocean). Such a canal would be a strategically valuable alternate to the present Suez Canal and would probably contribute greatly to the economic development of the surrounding area. The difference in elevation between sea level and the Dead Sea (30 miles away and 1286 feet below sea level) might also be used to generate hydroelectric power. The maximum depth of excavation to be encountered is on the order of 1500 feet. Conventional methods of excavation of this magnitude are prohibitively expensive, if indeed possible, but it appears that nuclear explosives could be profitably applied to this situation.

A total burn-spectrographic method has been applied to the determination of trace concentrations of silicon in plutonium. The sample is oxidized to plutonium dioxide, mixed with a germanium dioxide-graphite mixture containing tin internal standard, packed into cupped graphite electrodes, and burned to completion in a high amperage direct current arc. Plutonium spectral interference is minimized by optical means and by use of a less intense silicon line. The sensitivity is thereby decreased but is still sufficient to determine 25 ppm of silicon in plutonium. The precision of the method is estimated to be �8% (relative standard deviation) at the 270 ppm level and �14% at 40 ppm.

From introduction: This report is a revision to a previous edition: The information provided in Volume II describes programs, requirements, and procedures established by the Operator to minimize the probability of equipment failure, actions taken during any emergency to minimize radiation exposure dose to the general public and to plant personnel, and actions taken following a hazardous condition to prevent its recurrence.

Abstract: A limited study of the compound U₃Si₂ has been made in reference to its use as a prospective nuclear fuel in sodium cooled reactors.

From abstract: The Madelung constant and the inverse twelfth power repulsion factor have been calculated for the wurtzite structure for wide ranges of the crystal parameters and u.

From abstract: A development program was initiated to design, fabricate and test an absorber column with a 10 to 12 year lifetime, for use in the proposed LSGR.

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What is attempted here is to compute the energy absorbed in several elements from interactions with neutrons in the energy range of 0 to 14 Mev. In these calculations the results have been normalized to one neutron per square centimeter incident per gram of target material, thus making it a simpler matter to calculate energy absorbed in compounds containing these elements. In these calculations the single-collision approximation is assumed in that each neutron is considered to undergo only one collision in the sample, that scattered neutron escaping from the sample. The results are presented graphically for the elements hydrogen, carbon, nitrogen; oxygen: ·aluminum, ·silicon, germanium, tantalum, and bismuth. Plotted in these figures is the energy transferred per gram of target material per single neutron per square centimeter incident as a function of the-incident neutron energy.

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This report describes the Coupled NOFLOW-FIPDIF computer program which has been written to perform the following two related functions: (1) Determination of the temperature attained by reactor materials following a loss of coolant accident. (2) Evaluation of the fission product inventory which would exist at any time (following loss of coolant).

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In accordance with agreements reached at the Systems Analysis Meeting held between WANL, AGC and SNPO personnel at WANL on 6 April 1965, an equation set has been developed which describes the NERVA systems. The equations are documented herein.

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