From 1969 through early 1976, Oak Ridge National Laboratory was requested by the Westinghouse Advanced Reactors Division (WARD) to analyze various shields WARD designed for the Fast Flux Test Facility (FFTF). To develop the proper methodology for such a large and complex system, it was necessary to improve the basic cross-section data sets for sodium and iron and to devise calculational techniques which would allow some regions to be treated in detail and would also allow the analyses to be carried out in steps that could be coupled to each other. These requirements necessitated the performance of two types of experiments: measurements of radiation transport through bulk samples (simple geometry) of important FFTF materials; and measurements of radiation transport through mock-ups of specific geometric regions of the FFTF. The successful analyses of these experiments allowed the application of the derived data sets and various combinations and adaptations of the DOT discrete ordinates and MORSE Monte Carlo transport codes to the FFTF system itself. The first series of calculations for the full system revealed that a cavity surrounding the reactor vessel provided a pathway for neutrons to stream up to the head compartment. Also, fissions in fuel elements stored in the …

A new statistical analysis has been used to treat all of the results from the /sup 37/Cl-/sup 37/Ar solar neutrino experiment obtained since 1970 which are based on counting /sup 37/Ar using both energy and rise-time to characterize the decays. The results of this treatment are reported. Recent results in the development of the /sup 71/Ga-/sup 71/Ge and /sup 7/Li-/sup 7/Be solar neutrino experiments at Brookhaven National Laboratory are also reported.

One of the shortcomings of the method of discrete ordinates has been a tendency to generate negative estimates of inherently positive fluxes due to over-extrapolation. A new formulation presented here shows a repair of the shortcomings of previous methods to solve this problem by the introduction of an arbitrary parameter, theta. The theta-weighted difference method is seen as giving results as accurate as any while possessing the desired smooth convergence. The exact choice of theta is unimportant. 4 figures, 2 tables. (RWR)

Scylla IV-P is a 5-m linear theta pinch at the Los Alamos Scientific Laboratory primarily used to study end effects of linear theta-pinch plasmas. One method that may be used to reduce plasma end loss from linear theta pinches is to insert material end plugs. Two different assemblies that insert end plugs have been fabricated and installed on Scylla IV-P. The presence of the material end plugs have been found to increase the plasma confinement time by 20 to 30 percent; the plasma stability is increased (the m = 1 wobble is suppressed), and the neutron production is not degraded. The design of the end plug insertion mechanisms is described in some detail and information is presented on end plug erosion. Material eroded from the end plug must be either removed by the vacuum system or it plates out on the vacuum system surfaces. A condensed gas end plug has been proposed to eliminate problems associated with ablated solid material; a third end plug assembly for this is being designed which inserts a cryostat coated with a condensed gas. A prototype of this cryogenically cooled end plug (cryo-plug) has been fabricated and tested. These data are presented and the insertion …

This paper describes plasma engineering studies made in support of a revised version of a tokamak experimental power reactor (EPR). These include: (1) magnetohydrodynamic (MHD) equilibrium and stability calculations, which establish the ranges of ..beta../sub t/ and the corresponding MHD parameters; (2) particle and power balance calculations, which are used for sizing and trade-off studies; and (3) burn cycle dynamics calculations, which determine start-up and driving systems requirements and reactor net power output. The resulting EPR reference design is described.

The equilibrium field (EF) coil system for the Argonne Experimental Power Reactor (EPR) and the methods by which it has been designed are described. The number of coils, their placement, and the currents in them are fixed by considerations of the trade off between the stored energy in the coils and the closeness with which the required magnetohydrodynamic (MHD) equilibrium can be matched. The bulk of the equilibrium field is produced by superconducting coils outside the toroidal field (TF) coils. These coils are decoupled from the ohmic heating (OH) system. Normal conducting coils just outside the vacuum chamber are also provided for fine control. The amount of D-shapedness of the plasma cross section is found to be limited. The reference design EF coil system configuration is described, and the internal configuration of the conductor and implications of the EF coil system on the reactor burn cycle and on the driving system costs are discussed.

Aerosol samples were simultaneously collected at two street-level locations and the 16th floor, on two sides of a Manhattan city block. The results of PIXE analysis, together with CO and SO/sub 2/ data, show that the concentrations of substances emitted at street level (CO, Pb, etc) are significantly less at the 16th floor whereas particulate sulfur shows little variation. Other conclusions are presented.

Long-term dynamics of forest growth and succession and the effects of environmental modification can be studied using stochastic stand growth models. The result of simulations using these models is a set of stochastic time series for stand characteristics such as total biomass. Additional analysis is generally required to clarify behavior present in the time series. In this paper spectral analysis is used to elucidate differences in dynamics of perturbed and unperturbed forest stands as evidenced by comparison of peaks in the spectral density representing various types of cyclic behavior in the total biomass of the stand. A typical Appalachian deciduous forest stand area is considered. The consequences of three types of environmental perturbations are analyzed: a blight resulting in the elimination of a dominant species, a change in average annual temperature representing the greenhouse effect of gases released to the atmosphere, and a change in the growth rate of selected tree species due to increases in the concentration of atmospheric pollutants or to acid precipitation. The stand growth model was run for each type of environmental change as well as for unperturbed conditions. Simulations were made for a 1000 year time period. The power spectral density was estimated for the …

Separate abstracts were prepared for each of the 5 included sections. (MOW)

Separate abstracts were prepared for four of the included sections. (MOW)

Post-HCDA, core-debris behavior is considered in three locations: (1) within the reactor vessel, (2) within the cavity below the reactor vessel, and (3) within the concrete below the reactor cavity. In-vessel behavior is dominated by considerations of the fragmentation of molten fuel and steel on quenching in an excess of sodium to form particulate debris beds. In-vessel coolability depends primarily on the availability of sufficient horizontal surface area so that the particulate bed depth is not excessive and on the requirement that removal of small quantities of heat from the reactor vessel continues. Core debris behavior in the reactor cavity can be controlled in several different ways. An uncooled cavity liner could maintain its integrity for many days while the decay heat is absorbed by sodium boiloff from the cavity. An engineered cooling system in the cavity could result in the permanent coolability of core debris in the cavity. Such a system could be based on one of four general concepts, including (1) the cooled crucible concept, (2) the sacrificial barrier concept, (3) the stable barrier concept, and (4) the catch tray concept. Each concept has a different set of advantages and disadvantages. However, each would appear to be a …

Analyzing power and differential cross-section results are presented in tabular and graphical form for /sup 4/He(t,t)/sup 4/He elastic scattering from 7- to 14-MeV bombarding energy. The experimental procedure is described for measuring the analyzing powers.

Assuming that the new resonance ..gamma..(9.5) is a vector meson, its leptonic and hadronic decay widths are calculated in analogy to those of psi(3.1). Then, using the Breit-Wigner formula, the production cross section in e/sup +/e/sup -/ annihilation is predicted. The tensor dominance of the Pomeron, together with the vector dominance model, is invoked to estimate the photoproduction cross section.

Internal hydrogen embrittlement may be viewed as an extreme form of environmental embrittlement that arises following prolonged exposure to a source of hydrogen. Smooth bar tensile specimens of three stainless steels saturated with deuterium (approximately 200 mol D/sub 2//m/sup 3/) were pulled to failure in air at 200 to 400/sup 0/K or in liquid nitrogen at 78/sup 0/K. In Type 304L stainless steel and Tenelon ductility losses are a maximum around 200 to 273/sup 0/K; Type 310 stainless steel is not embrittled at this hydrogen concentration. A distinct change in fracture mode accompanies hydrogen embrittlement, with fracture proceeding along coherent boundaries of pre-existing annealing twins. This fracture path is observed in Tenelon at 78/sup 0/K even when hydrogen is absent. There is also a change in fracture appearance in specimens with no prior exposure to hydrogen if they are pulled to failure in high-pressure hydrogen. The fracture path is not identifiable, however. Magnetic response measurements and changes in the stress-strain curves show that hydrogen suppresses formation of strain-induced ..cap alpha..'-martensite at 198/sup 0/K in both Type 304L stainless steel and Tenelon, but there is little effect in Type 304L stainless at 273/sup 0/K.

The temperature dependence of embrittlement of type 304L stainless steel saturated with hydrogen at high pressure was studied. The charging condition was expected to accentuate property changes and changes in fracture mode reported previously without the complicating effects associated with cathodic charging. (GHT)

Neutron noise analysis measurements were made in three BWR-4 reactors under full-power conditions to determine the noise characterization spectra of the reactors with two different instrument-tube cooling configurations. Both configurations were designed to prevent flow-induced vibration of the instrument tubes and subsequent damage of fuel channel boxes caused by impacts of the tubes with the boxes. Noise spectra from these three reactors were compared with spectra previously obtained prior to changing the instrument-tube cooling configuration, and no evidence of impacting was found.