We subjected the Meteorological Data Acquisition (MEDA) remote station hardware to temperature, vibration, and road tests. The MEDA equipment was designed at the Lawrence Livermore Laboratory (LLL) for the Air Resources Laboratory (ARL). ARL supplied all MEDA sensors. The prototype system passed these tests.

Newsletter issued by the Advisory Council for Technical-Vocational Education in Texas discussing news, events, and other relevant information related to technical and vocational education for adults in Texas.

Neutronics information is summarized for several experiments in the irradiation facilities of the Oak Ridge Research Reactor (ORR). Comparisons are made between experimental data and results obtained from calculational models. Factors that significantly influence the neutronic characteristics of the irradiation facilities are identified, and experimental neutron dosimeter materials and techniques are described.

This report details the federal and state laws regarding animal baiting and fighting. In general, this report found three types of state statutes on this matter: specific legal prohibition aimed at stamping out a practice considered either distasteful, immoral, or a nuisance; general animal cruelty provisions enacted into law which may or may not be held applicable to baiting and fighting or any or all animals, and which may be not be enforced against those involved in such activities; and the absence of statutory restraints due either to open acceptance of animal baiting and fighting as a harmless activity or due to lack of concern over the matter.

This report describes the results of a study conducted by a "Pool Study Group" organized at ANL in mid-1975 to examine the present state of the air of design of pool-type LMFBRs. The study concentrated on examination of various design options used to date in the principle pool-type projects and design studies in this country and abroad, including the Phenix and Super-Phenix reactors (France), PFR and CFR (U.K.), RN-600 (U.S.S.R.) and EBR-II (U.S.A.). The objective of the report is to provide a step toward better understanding of the pool-type system and of the advantages and disadvantages of the various possible approaches to its design.

Tabulated data are presented for the radioactive waste generated and the status of the waste farms during the first quarter of 1976. (JSR)

The flow rate of neutral carbon atoms during the initial startup phase of an ohmically heated plasma in the FM-1 spherator was determined from the spatially resolved measurements of the carbon line radiation and independent measurements of spatial distribution of plasma density and electron temperature. This was accomplished by comparing the measured carbon line intensity with a numerical solution of time-dependent coupled differential rate equations for several carbon ionization states. The empirical flow rate of carbon atoms into the discharge, GAMMA/sub flow/(t), was found to be GAMMA/sub flow/(t) approximately equal to n/sub e/(t)/ tau/sub flow/, where tau/sub flow/ was 30-100 msec depending upon discharge conditions.

The objectives of the work are to develop mathematically and computationally founded for the design of highly efficient and reliable multidimensional neutron transport codes to solve a variety of neutron migration and radiation problems, and to analyze existing and new methods for performance. As new analytical insights are gained, new numerical methods are developed and tested. Significant results obtained include implementation of the integer-preserving Gaussian elimination method (two-step method) in a CDC 6400 computer code, modes analysis for one-dimensional transport solutions, and a new method for solving the 1-T transport equation. Some of the work dealt with the interface and corner problem in diffusion theory. (RWR)

The electromagnetic pulse (EMP) produced by a high-altitude nuclear detonation consists of a transient pulse of high intensity electromagnetic fields. These intense fields induce current and voltage transients in electrical conductors. Although nuclear power plant cables are not directly exposed to these fields, attenuated fields will couple some EMP energy to these cables. In the study described, theoretical and experimental techniques have been used to determine the EMP surges induced in several types of cables typically used in nuclear plants. It was found that unshielded lines such as power cables within the plant building may have EMP surge peaks as high as 88 kV induced between the cables and the earth. Shielded cables such as coaxial cables will have EMP surge peaks in the tens of volts. Cables located in electromagnetically tight conduit will have only small EMP-induced transients on the order of several millivolts or less.

A unitary Deck model with coupled K*..pi.. and Krho channels, including only one resonance in the Q region is constructed. Adjusting the resonance parameters, one achieves a satisfactory description of the experimental phase variations and structure in the mass spectra. The resonance is determined to belong to the J/sup PC/ = 1/sup + -/ SU(3) octet, and is thus the Q/sub B/. The relative coupling strength K*..pi../Krho is approximately 2/3.

Relaxation techniques which have been used in connection with the factorization iterative methods are reviewed. Known properties are summarized, and new ones are obtained. A precise meaning is given to the notion of iterative procedures of order q, and the two-parameters overrelaxation technique of Woznicki is shown to be a factorization iterative method of the second order; some consequences of this fact are developed. Other results include the refinement of known properties of the extrapolation principle and estimations of the powers of the Oliphant relaxation technique for consistently ordered matrices and of the Chebyshev technique for Stieltjes. 4 figures.

It is shown that the previously reported strong linear modulation of lower hybrid waves by low frequency fluctuations is actually a modulation of the lower hybrid cone trajectory. The changing trajectory has the appearance of an amplitude modulation when observed by a stationary probe.

The degree of subcriticality of a multiplying assembly having a spontaneous fission-neutron source may be inferred by inducing an additional change in multiplication and by following the flux profile through the course of this change to its final stationary state. It is important to assess the significance of noise effects insofar as they bias the estimate of initial subcriticality and as they place confidence limits on this estimate. A procedure is described for profile analysis which includes the effects of all noise sources. The procedure is more nearly equivalent to the traditional prompt-jump three-point analysis than to the more general inverse kinetics analysis. A code for extracting initial subcriticality and errors from a flux profile subject to an arbitrary noise level is provided.

Three different dosimeters were used to calibrate Savannah River Plant /sup 60/Co sources having intensities greater than 10/sup 7/ rads/hr. These dosimeters are (a) ceric sulfate dissolved in 0.4M H/sub 2/SO/sub 4/, (b) oxalic acid dissolved in water, and (c) a commercially available nylon film containing a radiochromic dye. Response per unit dose to these dosimeters is independent of radiation intensity at 10/sup 4/ to 10/sup 11/ rads/hr. The dosimeters were calibrated at 6.0 x 10/sup 5/ rads/hr with a /sup 60/Co source whose intensity was determined with the standard Fricke dosimeter. For the sources at 10/sup 7/ rads/hr or greater, intensities were calculated from slopes of linear plots of dosimeter response versus irradiation time. Individual dose rates varied from 1.0 x 10/sup 7/ to 4.6 x 10/sup 7/ rads/hr. Each source was calibrated with at least two different dosimeters. Relative standard deviations varied from 2 to 9 percent. A conservative estimate of the uncertainty in the accuracy of these dosimeters is 10 percent. Of the three dosimeters, the nylon film is easiest to use and is therefore recommended for future calibrations.

The objective of this program was to analytically and experimentally investigate the use of heat pipes in flat-plate solar collectors. Heat pipes are passive heat transport devices which utilize a closed evaporation-condensation cycle. Because of their high equivalent conductance, they appear to be well suited to transport heat from the solar absorber to an air or liquid distribution system. The program consisted of the following tasks: (I) Configuration Studies, (II) Parametric Performance Studies, (III) Economic Analysis, (IV) System Integration Studies, (V) Submodule Fabrication and Testing (in the laboratory), and (VI) Full-Scale Module Fabrication and Testing (using solar input). An additional Task VII, Feasibility Study of a Stationary Concentrator, was identified during the program and was also completed. In performing Tasks I through IV, various aspects of integrating heat pipes into flat-palte solar collectors were investigated. The results of these tasks were reported in the Annual Progress Report (Ref. 2) dated January 31, 1975. A summary of that program effort is included in the present report. The results of the experimental work conducted under Tasks V and VI are presented in this report. Under Task V, breadboard heat pipes were fabricated from sections of Roll-Bond panels and their heat transfer performance …

Vitrification of nuclear waste calcines using the storage canister as the melting crucible has been under development on an engineering scale in both radioactive and nonradioactive facilities at the Pacific Northwest Laboratory since 1968. Processing techniques, melting rates, canister designs, and the effects of the process on the canister and product are presented.

Methods used to control the radiological impact of the nuclear fuel cycle are described. This control is exercised through the application of a series of federal laws and regulations that are used as the basis for licensing nuclear facilities. The control is exercised more directly by the use of radwaste treatment equipment at the nuclear facilities to limit the release of radioactive materials. Federal laws and regulations are summarized and their applications in licensing actions are discussed. Radiological doses from materials released from licensed facilities are compared with doses from natural background. A series of cost/benefit engineering surveys are being made to determine the cost and effectiveness of radwaste systems for decreasing the release of radioactive materials from model fuel cycle facilities and to determine the benefits in terms of reduction in dose commitment to individuals and populations in surrounding areas.

A model is described for steady-state liquid-lithium flow on the inside of a spherical reactor cavity. The governing equations are derived and discussed together with the physical assumptions implicit in the formulation of the problem. Solutions are determined for different distributions and rates of mass supply from the outside through the porous wall to the inside of the cavity. The self-consistency of the model is demonstrated, and from computed flows it is concluded that inside a sphere of 1.5-m radius a liquid layer several millimeters thick can be maintained easily with a circulating flow of only a few kilograms per second. The thickness of the layer can be made nearly uniform over most of the sphere with relatively simple mass-supply distributions. The need for transient stability analysis is pointed out.

The diversity of equipment and operating conditions at a major national research and development laboratory requires a systematic, effective lubrication program. The various phases of this program and the techniques employed in formulating and administering this program are discussed under the following topics: Equipment Identification, Lubrication Requirements, Assortment of Lubricants, Personnel, and Scheduling.

Possible benefits that could accrue from actinide separation and transmutations are presented. The time frame for implementing these processes is discussed and the expected benefits are qualitatively described. These benefits are provisionally quantified in a sample computation.

Twenty-four people participated in the ISABELLE Cryogenic System Workshop which was held on June 2 and 3, 1976. The magnet cooling system for ISABELLE, as described in the new proposal, utilizes supercritical helium as the refrigerant instead of pool-boiling helium as in earlier proposals. This new and more cost-effective system was described in detail with discussion of the design parameters for the refrigerator itself, turbomachinery required and the refrigerant distribution system. The testing and prototype development program for ISABELLE cryogenic system components was also reviewed. A small cryogenic turbocompressor/expander system is now on order for testing with an ISABELLE half-cell (2 dipoles and 1 quadrupole).

The computer program, COMCAN, searches the fault tree minimal cut sets for shared susceptibility to various secondary events (common causes) and common links between components. In the case of common causes, a location check may also be performed by COMCAN to determine whether barriers to the common cause exist between components. The program can locate common manufacturers of components having events in the same minimal cut set. A relative ranking scheme for secondary event susceptibility is included in the program.

The ZONE computer program is a finite-element mesh generator which produces the nodes and element description of any two-dimensional geometry. The geometry is subdivided into a mesh of quadrilateral and triangular zones arranged sequentially in an ordered march through the geometry. The order of march can be chosen so that the minimum bandwidth is obtained. The node points are defined in terms of the x and y coordinates in a global rectangular coordinate system. The zones generated are quadrilaterals or triangles defined by four node points in a counterclockwise sequence. Node points defining the outside boundary are generated to describe pressure boundary conditions. The mesh that is generated can be used as input to any two-dimensional as well as any axisymmetrical structure program. The output from ZONE is essentially the input file to NAOS, HONDO, and other axisymmetric finite element programs. 14 figures. (RWR)

The high-pressure safety program at Lawrence Livermore Laboratory, Livermore, California, has been successful in preventing lost-time high-pressure accidents over the past 12 years. Program organization, personnel training and qualification, pressure vessel design criteria and documentation, and pressure testing and inspection are discussed.