The results of the analysis of {approx} 1000 {nu} events of the type {nu} + N {yields} {mu}{sup -} + hadrons from the NAL dichromatic beam are presented. Distributions in terms of the scaling variables x = Q{sup 2}/2o{nu} and y = {sup E}n/E{sub {nu}} are presented. The x distribution is compared with F{sub 2}{sup ed} (x) from SLAC; the Q{sup 2} distribution is tested for the presence of the propagator term F{sub 2}(x) {yields} F{sub 2}(x)/(1 + Q{sup 2}/2){sup 2}; and the y distributions are fit to the form d{sigma}{sup {nu}N}/dy = 1 + a(1-y){sup 2}. A smaller amount of {bar {nu}} data will also be presented.

Included are descriptions of welding methods and joint design, welding equipment, and qualification tests. (DG)

As a result of the recent concern by environmentalists, the hypothetical accident thermal test can no longer be performed by simply burning gasoline in an open pit. The uncontrolled open pit technique creates thick, dense, black clouds of smoke which are not permitted by local authorities. This paper deals with the design of the fire test facility and the techniques used to eliminate the smoke plume. The techniques include the addition of excess air to the fire in combination with a spray of water mist near the fuel surface. The excess air technique has been used successfully in an experimental setup; it was found that the temperature could be controlled in the neighborhood of the required 1475 degrees F environment and the smoke could be reduced to very low levels. The water spray technique has been successfully used by others in similar applications and, on completion of a permanent fire test facility at Mound Laboratory (anticipated July, 1974), test results will be available. The water is believed to interact with the combustion reaction to provide more complete combustion. The permanent facility will be a 10 x 10 ft cement block enclosure lined with firebrick. It will be 8 ft high …

Design of finned casks for dissipation of heat from radioactive decay usually requires reliance on generalized correlations in the literature which do not necessarily apply to the specific cask design. A correlation was developed, based on temperature profile measurements, for the design of upright cylindrical casks with vertical fins for convective and radiant heat transfer to ambient air. Temperature data at various heat loads were obtained for two different cask sizes of the same basic design. Each cask is mounted on a steel pallet and contained within a steel mesh cage. The smaller cask, which has 23 fins, has been approved (DOT-SP-6321) for shipment of up to 1400 W (th), and approval is being obtained (AEC AL USA/9503 BLF) for shipment of up to 3500 W heat load in the larger, 60-fin cask. The applicable theoretical equations were fit to the temperature data for both casks by simply adjusting the value used for the number of fins. The resulting correlation provides a reliable method for interpolation and extrapolation and for design of similar finned casks.

None

From meeting on fission product nuclear data; Bologna, Italy (26 Nov 1973). Applications of fission product nuclear data and data on the fission process in uranium and transuranic elements are required for radiation protection of personnel and the general population for the following situations: to determine the toxicity to exposed individuals from externally located isotopes in the environment or in the fuel cycle; to determine the toxicity caused by deposition of radioactive materials in living systems; to estimate the radiation dose to patients during medical application of injected radioisotopes for diagnostic or therapeutic means; during the use of sealed sources for implantation in living tissue (brachytherapy); during the use of sealed sources at a distance from the patient for therapeutic purposes (teletherapy); to determine the environmental pathways for uncontrolled release of radioactive materials into biosphere; and for personnel protection during the applications of radioisotopes in medicine, biology, agriculture, and industry, including gamma ray and neutron radiography. It was concluded that available nuclear data are adequate for these purposes. (CH)

None

None

From thirteenth international conference on thermal conductivity; Lake Ozark, Missouri, USA (5 Nov 1973). The safe burial in soil of a radioisotope heat source is an extremely complex problem, influenced by many parameters, including soil particle size, moisture content, weathering, density, inhomogeneities such as rocks and vegetation, soil disturbance upon impact, soil composition, and location on the earth. Precise descriptions of an accidental burial environment are in general impractical, if not impossible. Use of available analytical solutions simply to bracket a problem is less desirable than an analysis which treats directly the problem at hand. However, in the light of the difficulty in predicting accurately the post-impact environment, these approximate, bounding, relatively easy expressions provide a reasonable means for the design and/or safety evaluation of radioisotopic fuel capsules. More elaborate treatments probably would add little to the confidence in the results. (auth)

From international metallography society symposium on speciment preparation for metallography; Los Angeles, California, USA (23 Sep 1973). An evaluation of the effectiveness of plutonium metallography reveals inadequacies in electrolysis preparation techniques. The probable causes and the approaches to the problems that have been proposed by the participating laboratories over the past two decades are reviewed. A brief history of the metal is included. (auth)

None

The tower is a 180-ft tall steel-frame experimental oil shale processing retort structure with heavy process equipment on various levels. The structural response of the tower to the ground motion from Project Rio Blanco is analyzed and the necessary structural modifications described. (TFD)

None

>A laser method for recovery of deuterium or tritium from water is proposed. The two-step photolysis method utilizes a known coincidencc of the P/ sub 1/(8) line of the DF laser with HDO and D/sub 2/O absorption lines coupled with a water filtered xenon flash lamp to selectively photolyze HDO and D/sub 2/O in the presence of H/sub 2/O. CO is to be added to the photolysis mixture to remove the O atom from the OH photolysis product. The isotopic material is to be collected as D/sub 2/. The reaction kinetics for this experiment has been modeled with a computer calculation based on rate processes. The dependence of isotopic selectivity on various vibrational energy transfer processes is discussed. (auth)

The role of management in the responsibility for training personnel in the fundamentals of safety and accident prevention is discussed. Program for radiation protection, with emphasis on criticality safety, are discussed briefly. (CH)

None

None

From Winter meeting of American Society of Mechanical Engineers; Detroit, Michigan, USA (11 Nov 1973). The radiological'' and common cause risks'' involved in transporting radioactive materials are briefly discussed. (TFD)

From ANS topical meeting on gas-cooled reactors: HTGR and GCFBR; Gatlinburg, Tennessee, USA (8 May 1974). The high-temperature gas-cooled reactor power station has all of the potential environmental impacts associated with any large nuclear station. Construction impacts can be minimized by proper planning and are usually of limited duration. The potentially most significant impacts of station operation result from the operation of the heat dissipation system. The use of cooling towers is assumed. The effects of salt deposition, fogging, and icing are expected to be minor. The magnitude of the adverse effects caused by intake and discharge such as entrainment of eggs, larvae, and fish and chemical impacts from blowdown can only be assessed for a specific site but may be signlficant. The impact of radionuclide releases, constrained by the as-low-as- is-practicable criteria, is small. The only potential environmental advantage over other reactor types is lower consumptive water use for the same net electric power production. (auth)

None

None

From symposium on pore structures and properties of materials; Prague, Czechoslovakia (18 Sep 1973). Several processes are known to produce lattice vacancies in sufficient excess of the thermal equilibrium concentration that they precipitate out as voids. In the case of certain nuclear transmutations, a solid solution of gas is simultaneously produced at a concentration corresponding to a high equilibrium pressure and, if this gas diffuses into the voids, the equilibrium shape for the void is a thin flat cavity. Transmission electron microscopy was used to examine both the nucleation of such voids in neutron- irradiated boron carbide and their transformation to more compact shapes during fission gas release. (auth)

None

From third international conference on many-body- reactions; Zakopane, Poland (20 Jun 1972). The NAL Aecelerator project is described. Other new accelerator projects including polarized proton acceleration at the Argonne 2GS, the 2.5 GeV electron-positron colliding beams SPEAR, positron-electron-proton (PEP) colliding beams, and the ISABELLE projects are briefly discussed. (WHK)