Three alternatives to decommission the Heavy Water Components Test Reactor (HWCTR) have been analyzed as summarized in Table 1. The protective confinement approach is advantageous as long as current activities onsite limit access by the general public; excellent confinement of the residual activity is provided by in situ dry storage as the radiation from {sup 60}Co diminishes. Entombment provides the most-secure confinement of the activity but at some increased cost. Dismantling HWCTR has no apparent advantages other than a demonstration at the Savannah River Plant site, because of the long-term commitment to safeguarding radioactive material; the relative cost is high. The induced radioactivity in HWCTR is current 2.3 {times} 10{sup 4} Ci; general area radiation levels are typically 3 mR/hr. In 35 years, the decay of {sup 60}Co will lower the radiation levels by a factor of 100, and the remaining radioactivity will be 2 {times} 10{sup 3} Ci of {sup 63}Ni. Minimal offsite effects are calculated to result after postulated structural failures to the decommissioned HWCTR facility. Flexibility and aesthetics favor dismantlement, but these criteria are considered less significant than public radiation dose, cost, and land area committed.

The Earl Warren Legal Institute, part of the University of California at Berkeley, is a center for law-related interdisciplinary research and public service in areas of national social concern. Since 1975, we have worked with the U.S. Department of Energy and Lawrence Berkeley Laboratory on various projects addressing energy policy and environmental issues. We are now engaged in a major effort to identify current legal, economic and institutional obstacles to commercial development and use of geothermal energy sources. Geothermal resources--heat reservoirs beneath the earth's surface--have received increasing attention in recent years of growing energy consciousness, and much progress has been made toward understanding their nature, extent and uses. Encouraged by federal and state development programs, there now exists an active and growing community of geologists, geophysicists, engineers, drilling companies, developers and end-users of geothermal heat. However, Department of Energy studies indicate that current knowledge and available technology would support substantially broader use of the resource, particularly by private sector commercial, industrial and agricultural concerns. Accordingly, we are now seeking to determine the knowledge and attitudes of such entities toward geothermal use; the factors which will influence decisions to utilize geothermal or not; the perceived obstacles, if any, to expanded use …

To supply the heat input required by space-borne cryogenic refrigerators, a possible design for a reliable Pu-238 radioisotope heat source, based on state-of-the-art technology, is described. The isotope heat source, which makes use of existing fuel elements, would replace electrical heaters powered by solar panels and batteries, without requiring redesign of the refrigerators. The heat source contains all necessary safety features, and also a simple thermal control system to permit refrigerator shut-down for indefinite duration. A system for thermal interfacing with the spacecraft, the booster, and ground support is also described. The isotope heaters are compared with solar-electric heaters for the same application, and found to result in very significant weight and size savings.

Magnetic surfaces for a plasma with a helical current perturbation approximately epsilon$sup 2$ are destroyed by toroidal effects or by a second current perturbation, of incommensurate helicity, and the behavior of magnetic field lines becomes stochastic in layers of relative width epsilon$sup -$/sup l/ exp (-$pi$/2 epsilon). (auth)

The reactor performance is considered for intensely beam-driven tokamak plasmas with 50:50 D-T composition maintained by neutral-beam injection of both D and T, together with plasma recycling. The D and T are injected with equal intensity and velocity. This mode of operation is most appropriate for high-duty- factor, high-power-density operation, in the absence of pellet injection. The isotropic velocity distributions of energetic D and T ions (for multi-angle injection) are calculated from a simple slowing-down model, but include a tail above the injection velocity. The neutron source characteristics are determined from fusion reactivities calculated for beam-target, hot-ion, and thermonuclear reactions. For conditions where Q approximates 1, beam-target reactions are dominant, although reactions among the hot ions contribute substantially to P/sub fusion/ when n/sub hot//n /sub e/ greater than or equal to 0.2. (auth)

Studies are presented of personnel exposures to $sup 252$Cf neutrons and gamma radiation during dosimetry experiments in mouse phantoms, fission foil detectors, and small tissue equivalent ionization chambers. Sensitivity of film badge emulsions to observed levels of $sup 252$Cf neutrons is discussed. Long- term personnel exposure histories are presented. Comparisons are made between neutron dose calculated from observed neutron-gamma ratios and the dose observed in neutron emulsions. Shielding used during experiments is described. (auth)

The report discusses the four major research areas of this program: diagnostic studies of CTR plasmas, laboratory spectroscopy and calibration at short wavelengths, theoretical computation of transition probabilities for highly ionized atoms, and instrument development for short wavelength studies of CTR devices. Using existing instruments, diagnostic studies are under way at Versator and Elmo Bumpy Torus. A facility has been completed for the sensitivity calibration of spectrometers down to 300 A as complete units. The development of computer programs necessary for transition probability calculations is ninety percent complete. An f/20 forty cm focal length concave grating spectrometer has been constructed utilizing very high vacuum techniques to reduce contamination of plasma devices and calibration sources such as SURF II at NBS. New designs for grazing incidence monochromators have been developed.

In the course of the Cascade Improvement Program, many component equipment parts will be electroplated with nickel for corrosion protection. The maximum hardness which will be acceptable in the electroplated deposit is specified in Union Carbide's Job Specification JS-1396, Revision 3, entitled Electroplated Nickel Coatings on Steel Parts. The hardness specification is intended primarily as a control over both organic and inorganic impurities in the deposit. This report covers a study evaluating several of the numerous controllable variables which influence the hardness of the nickel plate deposited from a Watts-type bath. The variables tested were: 1) bath composition, 2) pH, 3) current density, 4) anode-cathode area ratio, and 5) bath temperature. Within the tested ranges of the variables studied, the pH and current density had the most influence on the plate hardness. The softest deposit was obtained with a bath pH of 1.5, a current density of 30 to 40 amperes/square foot, and with the anode-cathode area ratio in the range of 3:1 to 1:1. (auth)

Progress is reported in studies on the synthesis of $gamma$-emitting analogs of aliphatic amino acids which may be clinically useful for the localization of pancreas. The $gamma$ radionuclides to be incorporated include $sup 131$I, $sup 123$I, and $sup 77$Br. Preparation of $beta$-chloro-$alpha$- aminobutyric acid which on interchange with $sup 131$I would yield I-for-methyl analog of valine is reported. This interchange is being currently studied. The bromo derivative was also prepared and should be a more reactive substrate for halogen interchange reactions or direct isotope exchange with $sup 77$Br. Concurrently, the synthesis of the I-formethyl analog of leucine is underway. In this connection, two intermediates were prepared, namely, allyl glycine and $alpha$-amino-$gamma$-valeralactone . HCl. (auth)

Aspects of low-dose, low-temperature irradiation experiments, and elevated-temperature experiments are reviewed. Information and data are included on methods of determining lattice atom displacement thresholds, lattice damage rates measured by changes in resistivity, ion damage, and neutron damage. (JRD)

Electron irradiation (2 MeV, up to 6 x 10$sup 18$ e/cm$sup 2$) decreased the yield stress of iron single crystals in the temperature range from 4.2 to 80$sup 0$K. The softening effect was highly dependent on the tensile axis orientation. The temperature and strain rate dependency of the yield stress was increased by the irradiation. The annealing of the softening took place between 90 and 150$sup 0$K. The observation is consistent with an intrinsic solid solution softening mechanism based on the enhancement of screw dislocation motion due to dispersed interstitials. (auth)

A standard is presented to delineate the requirements for the design, materials, fabrication, examination, acceptance testing, and delivery of a cold trap assembly to remove impurities from liquid sodium by crystallization. (auth)

Tracer self-diffusion coefficients were measured as functions of temperature and deviations from stoichiometry. The arc-transfer technique of crystal growth was found to produce crystal of Co/sub 1-x/O of essentially the same purity as the starting Co rod, and the quality was comparable to commercially available crystals grown by Verneuil process. Measurements at x = 0.005 in Co/sub 1-x/O showed the Co tracer self-diffusion coefficient to be D = 3.88 x 10$sup -4$ exp (--31600 +- 2400/RT) cm$sup 2$/s between 1037 and 1350$sup 0$C. This activation energy is in agreement with measurements made in air, if proper compensation is made for the effect of variation in stoichiometry. Measurements on crystals having deviations between 0.002 and 0.008 at 1150$sup 0$C showed the diffusion coefficient to depend on p/sub O$sub 2$/ as D = 9.74 x 10$sup -9$ p/sub O$sub 2$//sup 1/(3.59)/ cm$sup 2$/s, where p/sub O$sub 2$/ varied between 10$sup -2$.$sup 5$ and 10$sup -0$.$sup 25$ atm. Comparison with thermogravimetric and electrical conductivity measurements confirms that the defects responsible for Co diffusion in the range of temperature and p/sub O$sub 2$/ of this investigation are singly ionized cobalt vacancies. The Co tracer self-diffusion coefficients in single crystals are nearly identical to those …

The requirements placed on a tokamak ohmic heating system (i.e. loop voltage) to initiate the plasma become more severe as the size increases because of the current density decrease. During the startup phase even small concentrations of low Z impurities can affect the plasma energy balance very substantially and have very important effects on the evolution of the discharge. The startup phase has been studied using a simple zero dimensional computer code. Because the dominant energy loss mechanisms during startup, radiation, and ionization are a volume effect, the zero dimensional code was adequate to treat this phase. The results of this study which have been applied to TFTR indicate that the plasma evolution is a sensitive function of the applied loop voltage, impurity concentration, initial filling pressure and the manner in which gas is fed into the discharge. (auth)

The gross properties of a high-density (n approximately equal to 10$sup 27$ m$sup -3$), small-radius, (r = 10$sup -4$ m) gas-imbedded Z pinch have been examined considering only classical processes. The rate equation using only ohmic heating along with bremsstrahlung and radial heat transport shows that ohmic heating will rapidly take the pinch to thermonuclear temperatures for currents, I, greater than 1 MA. The radial heat loss for the pinch is very small for I greater than 1.5 MA. This suggests that the pinch could tolerate being driven to a nearby wall by an m = 1 kink. The laser technology for initiation of the small-diameter filament and the high-voltage technology for giving a 30-ns rise to a MA or more are available now. Some reactor considerations have been included. (auth)

If a beam-driven D--T tokamak reactor is operated at the maximum density allowed both by pressure limitation and by adequate neutral-beam penetration, the 14-MeV neutron wall loading increases approximately linearly with magnetic field or vertical elongation of the plasma. With elongation = 3, B/sub tmax/ equals 15T, W/sub beam/ = 200 keV, Q approximately 1.0, maximum wall loading is about 5 MW/m$sup 2$. (auth)

A standard is presented which covers recommended practices in the planning, coordination, and administration of shipments of critical components and equipment for nuclear facilities. The standard supplements and is additive to the rules and regulations of freight classifications and tariffs governing carriers and shipping, and has the purpose of minimizing the liklihood of physical damage or deterioration of critical components and equipment due to collision, upset, shock, vibration, corrosion, or other conditions of the transport environment. (auth)

This booklet contains the abstracts of all active U. S. patents on technology items that originated at ANL, the applicability of which is not limited to nuclear reactors. Also listed are the titles of all ANL-originated nuclear-related U. S. patents that are still in force. Selected technology items for which patent applications have been filed and are available for licensing are included in several categories. Categories included in this booklet are as follows: atmospheric and earth sciences; biological and medical sciences; chemistry and chemical engineering; cryogenics and superconductivity; electronics and electrical engineering; energy conversion; measurements and controls; methods and devices; materials and fabrication; physics, accelerators and fusion; and selected nuclear-related technology. (RWR)

Brief discussions of research progress on the following topics are given: (1) lasers and laser applications, (2) advanced energy systems, (3) science and technology, and (4) national security. Some experiments on the in- flight laser irradiation of ammonia pellets are discussed. (MOW)

A brief review of the TFTR is given in terms of the physical size of the experiment in relation to existing and future tokamaks. Some break-even criteria are mentioned. (MOW)

Included are 127 abstracts and summaries of papers and reports published or presented at scientific meetings during the reporting period, which extends from August 31, 1974 to October 31, 1975. The primary areas of study are the liquid-metal fast breeder reactor program, the gas cooled fast breeder reactor program, the controlled thermonuclear reactor program, the high-energy accelerator shielding program, and the defense nuclear agency program. (BJG)

The Idaho Chemical Processing Plant (ICPP) discharges low-level waste and chemical waste directly to the Snake River Plain aquifer through a 600-foot (180 meter) disposal well. Most of the radioactivity is removed by distillation and ion exchange prior to being discharged into the well. During 1971 to 1973, the well was used to dispose of 404 curies of radioactivity, of which 389 curies were tritium (96 percent). The average yearly discharge was about 300 million gallons (1.1 x 10$sup 9$ liters). The distribution of waste products in the Snake River Plain aquifer covers about 15 square miles (30 square kilometers). Since disposal began in 1952, the wastes have migrated about 5 miles (8 kilometers) downgradient from discharge points. The perched ground-water body contains tritium, chromium-51, cobalt-60, and strontium-90. Radionuclides are subject to radioactive decay, sorption, and dilution by dispersion in the aquifer. Chemical wastes are subject to sorption and dilution by dispersion. Waste plumes south of the ICPP containing tritium, sodium, and chloride have been mapped and all cover a similar area. The plumes follow generally southerly flow lines and are widely dispersed in the aquifer. The waste plume of strontium-90 covers a much smaller area of the aquifer, about …

Physician acceptance of computer-enhanced radionuclide scan results, presented in the form of small Polaroid pictures, has been very limited for a number of subjective reasons. A new recorder was designed and constructed that presents the results of computer augmented scans through a medium that is quite familiar to doctors, the standard 14 in. x 17 in. x-ray film. (auth)

The skin thickness of blisters formed on polycrystalline niobium by $sup 4$He$sup +$ irradiation at room temperature for energies from 15 to 80 keV have been measured. Similar measurements were conducted for 10 keV $sup 4$He$sup +$ irradiation at 500$sup 0$C to increase blister exfoliation, and thereby allow examination of a larger number of blister skins. For energies smaller than 100 keV the skin thicknesses are compared with the projected range and the damage- energy distributions constructed from moments interpolated from Winterbon's tabulated values. For energies of 10 and 15 keV the projected ranges and damage- energy distributions have also been computed with a Monte Carlo program. For energies larger than 100 keV the projected ranges of $sup 4$He$sup +$ in Nb were calculated using either Brice's formalism or the one given by Schiott. The thicknesses for 60 and 80 keV, and those reported earlier for 100 to 1500 keV correlate well with calculated projected ranges. For energies lower than 60 keV the measured thicknesses are larger than the calculated ranges.