The objective of this investigation was to establish the allowable design loads (tension, shear, and combined load) for expansion bolts to be installed in regular 4000 psi mix concrete, Magnetite 5000 psi mix concrete, and Steel Shot 5000 psi mix concrete at the Fast Flux Test Facility. The test loads included Static Loads and Alternating Loads which simulate the dynamic loads of vibratory equipment and dynamic earthquake loads.

An exploratory research effort to find new molecular lasers in the 7-16 ..mu..m wavelength range, in particular lasers with wavelengths at 7.7, 8.6, and 16 ..mu..m wavelengths, is described. The specific initial objectives were: (1) to explore Raman scattering of CO/sub 2/ radiation in a liquid and molecular gas and (2) to explore chemically excited metal fluorides as laser candidates for the 12-16 ..mu..m wavelength range.

Studies of fusion reactors applied to synthetic fuel (synfuel) production have included detailed nucleonic analyses. Scoping studies were first performed to satisfy constraints such as net tritium breeding, and optimization of energy production in high-temperature vs moderate-temperature blanket regions. Detailed characteristics of a chosen reference design were then computed, including spatial distributions of kerma, dpa, hydrogen and helium production, and tritium breeding. The reference design provides a breeding ratio of 1.11 while depositing 42% of the recoverable energy in the high-temperature region used as a thermochemical process heat source. At a 1-MW/m/sup 2/ first-wall neutron loading, displacement damage and helium production in steel are a maximum of 11 dpa/yr and 111 appm/yr, respectively.

This report presents a test program for the Niland Geothermal Test Facility. It contains a detailed description of 18 tasks. Each of these tasks discusses the objectives, justification and relation to future design, general test procedures, test conditions, required experimental measurements, and methods of calculation and expected results. Implementation of these tasks will provide the basic information necessary for the design, construction, and initial operation of a 50-MWe geothermal demonstration plant.

None

This directory is designed to aid effective communication throughout the National Science Foundation's Trace Contaminants Program, Research Applied to National Needs. The majority of the participants in the Program are represented by name, address, telephone number, and a very brief description of research interest. The directory has five major divisions to facilitate its use. Section I contains a listing of the program managers associated with the NSF-RANN Trace Contaminants Program. Section II lists the principal investigators, co-principal investigators, and coordinators of each of the research grants in the Program. Section III lists the personnel by individual projects. Section IV contains a total alphabetic listing complete with project titles and Section V contains a keyword index. This directory is maintained by the Toxic Materials Information Center as part of the Environmental Resource Center of the Information Center Complex, Information Division, Oak Ridge National Laboratory.

A cost/benefit study was made to determine the cost and effectiveness of radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model nuclear fuel reprocessing plant which processes light-water reactor (LWR) fuels, and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist in defining the term as low as reasonably achievable in relation to limiting the release of radioactive materials from nuclear facilities. The base case model plant is representative of current plant technology and has an annual capacity of 1500 metric tons of LWR fuel. Additional radwaste treatment systems are added to the base case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The cost for the added waste treatment operations and the corresponding dose commitments are calculated for each case. In the final analysis, radiological dose is plotted vs the annual cost for treatment of the radwastes. The status of the radwaste treatment methods used in the case studies is discussed. Much of the technology used in the advanced cases is …

Fish impingement monitoring data for the years 1974 and 1975 pertaining to the Nine Mile Point Unit One, which began commercial operation in December 1969, were analyzed by the most practical qualitative and quantitative methods. The mathematical models used in describing the fish kill rates showed a marked improvement over the previous assumptions that fish kills (by species) can be considered as random events independent over time. However, with more accurate estimates on fish kills now available, it is still not possible to determine the significance of these fish kills. The results showed that predictions were higher than those observed. The data acquired, method of analysis, and results obtained are presented in detail along with our recommendations and conclusions.

This is the third quarterly progress report. The LWR Fuel Recycle Program is designed to assist in the commercialization of the LWR fuel cycle. Included in this program are both activities in support of specific design studies and other activities of more general applicability to fuel recycle technology. The following are reported in this document: economic and environmental documentation, spent fuel receipt and storage, head end processes, off-gas treatment, Purex process, finishing processes, environmental effects, and general support. (DLC)

Various models of large LMFBRs, based on cylindrical and hexagonal geometries, are examined in regard to application to nuclear power peaking analysis. It is shown that the general behavior of power distributions during burnup in these large reactors implies that power shaping by control rod movement is desirable for minimizing the peaking factor. Due to current limitations of available three-dimensional computer codes, one- and two-dimensional models were used to test general assumptions of power shaping. However, it is demonstrated that these models are not appropriate for more accurate power peaking analysis. Comparison of results for nuclear power peaking factors in cylindrical and hexagonal geometries shows that the use of annular rings of control poison in the cylindrical models does not provide a realistic representation of banks of control rod assemblies.

A time-of-flight (TOF) atom-probe field-ion microscope (FIM) designed for the study of defects is described. This atom probe features: (1) a variable magnification internal-image-intensification system; (2) a liquid-helium goniometer stage; (3) a low-energy (less than or equal 3 keV) gas-ion gun for in-situ irradiations; (4) an ultra-high vacuum (approximately 3.10/sup -10/ torr) chamber; (5) a high vacuum (approximately 10/sup -6/ torr) specimen-exchange device; (6) a Chevron ion detector; and (7) an eight-channel digital timer with a +-10 nsec resolution for measuring the TOFs. The entire process of applying the evaporation pulse to the specimen, measuring the voltages, and analyzing the TOF data is controlled by a computer. With this system we can record and analyze 600 TOFmin. Results on unirradiated specimens of molybdenum, tungsten, W/25 at. % Re, Mo/1.0 at. % Ti, Mo/1.0 at. % Ti/0.08 at. % Zr and a special low swelling stainless steel alloy (LS1A) demonstrate the instrument's ability to quantitatively determine concentrations at the 5.10/sup -4/ at fr level and to determine their spatial distribution with a resolution of a few angstroms.

Various data on charmed meson resonances are discussed including decay modes, masses, widths, mass differences, matrix elements, branching ratios, cross sections, and the Dalitz plot. (JFP)

A development program is being carried out to obtain information applicable to the SYNTHOIL process for converting coal to liquid fuel of low sulfur content. This report presents information on (1) the design of a calorimeter to measure heat of reaction of hydrogen with coal slurries, (2) the design of apparatus and calculations for measuring coefficients of heat transfer from SYNTHOIL process feed and effluent products to process vessel walls, (3) tests on the use of additives to facilitate the removal of solids from oil produced in coal liquefaction processes, and (4) the design and construction of a test unit for evaluating new catalysts for coal liquefaction processes.

The historical development of quantum mechanics is described with emphasis on the Moessbauer effect. (JFP)

A complete substitution of iron for nickel was obtained by splat-cooling in amorphous alloys of composition (Ni/sub 100-y/Fe/sub y/)/sub 79/P/sub 13/B/sub 8/. Results of high-field magnetization (up to 70 kOe), ac and dc low-field susceptibility, Curie temperature, and resistivity measurements over a temperature range of 1.7 to 300/sup 0/K are reported. The Ni/sub 79/P/sub 13/B/sub 8/ alloy is not ferromagnetic, but the magnetization behavior as a function of field and temperature is typically that of alloys in the critical concentration range for ferromagnetism. The Fe/sub 79/P/sub 13/B/sub 8/ alloy is ferromagnetic with a Curie temperature T/sub c/ of 616/sup 0/K. For y = 1 at. percent, the Fe atoms are magnetic. The variation of the moment per Fe atom as a function of y is discussed. When y is increased, the Ni atoms are likely to be polarized progressively and the moment per Ni atom would be roughly constant for y equal to or greater than 30 at. percent. Various magnetic behaviors were defined as a function of the Fe content. The value of T/sub c/ reaches a maximum for y similarly ordered 90 at. percent and extrapolates to zero for y similarly ordered 7 at. percent. Alloys within the …

The paper is intended to review and critically discuss microscopic integral cross section measurement and calculation data for fundamental reactor dosimetry benchmark neutron fields. Specifically the review covers the following fundamental benchmarks: (1) the spontaneous californium-252 fission neutron spectrum standard field; (2) the thermal-neutron induced uranium-235 fission neutron spectrum standard field; (3) the (secondary) intermediate-energy standard neutron field at the center of the Mol-..sigma sigma.., NISUS, and ITN--..sigma sigma.. facilities; (4) the reference neutron field at the center of the Coupled Fast Reactor Measurement Facility (CFRMF); (5) the reference neutron field at the center of the 10 percent enriched uranium metal, cylindrical, fast critical; and (6) the (primary) Intermediate-Energy Standard Neutron Field.

Results of emf measurements on Na/sub 2/O solid electrolytes in binary compounds with Cr/sub 2/O/sub 3/, FeO, and NiO are presented along with thermodynamic properties of these compounds. It was found that reliable thermodynamic data for compounds of NaCrO/sub 2/, Na/sub 2/FeO/sub 2/, NaFeO/sub 2/, Na/sub 2/NiO/sub 2/, and NaNiO/sub 2/ at 500 to 800/sup 0/ can be obtained by using emf measurements with solid electrolyte cells. The pretreatment of heating the cells in a vacuum of 10/sup -2/ torr at 500/sup 0/C or above for about 12 hours causes the emf dependence on temperature to be very small. The measurements were carried out over the temperature range in which no phase transformations occurred, the ..delta..C/sub p/ for the compounds involved was reasonably considered as approximately zero. Linear emf-temperature plots were therefore expected for these cells and the equation of ..delta..G/sup 0//sub f/ was indeed valid for constant values of ..delta..H/sup 0//sub f/ and ..delta..S/sup 0//sub f/. The formation of compound NaCrO/sub 2/ is thermodynamically favorable in a sodium loop made of austenic stainless steels. The critical oxygen concentration for the formation of NaCrO/sub 2/ shows that it is stable in liquid sodium in temperature range from 400 to 1100/sup …

A conceptual design has been developed for a Tokamak Experimental Power Reactor to operate at net electrical power conditions with a plant capacity factor of 50 percent for 10 yr. The EPR operates in a pulsed mode at a frequency of approximately 1/min, with an approximately 75 percent duty cycle, is capable of producing approximately 72 MWe and requires 42 MWe. The EPR vacuum chamber is 6.25 m in major radius and 2.4 m in minor radius, is constructed of 2 cm thick stainless steel, and has 2 cm thick detachable, beryllium-coated coolant panels mounted on the interior. A 0.28 stainless steel blanket and a shield ranging from 0.6 to 1.0 m surround the vacuum vessel. Sixteen niobium-titanium superconducting toroidal field coils provide a field of 10 T at the coil and 4.47 T at the plasma. Superconducting ohmic heating and equilibrium field coils provide 135 V-s to drive the plasma current. Plasma heating is accomplished by 12 neutral beam injectors which provide 60 MW.

The North Stanley Polymer Demonstration Project is a cooperative venture between Kewanee Oil Company and ERDA. The project is the result of a response to a request for proposals for secondary oil recovery by controlled waterflooding. The objective of the project (to be completed in June 1978) is to demonstrate the efficiency and economics of recovering tertiary oil from a highly heterogenous reservoir (which has been successfully waterflooded, but is nearing the economic limit) by injecting a polymer slug of tapered concentrations to improve the sweep efficiency of the reservoir. The project will be a true field test as it encompasses, 1010 productive acres and 72 million barrels of pore volume, utilizes the current producing and injection wells, and has a well-defined producing history which can be used as a baseline for judging project response. (DLC)

A direct-electrical-heating apparatus has been designed and fabricated to investigate those nuclear-fuel-related phenomena involved in the gap closure-bridging annulus formation mechanism that can be reproduced in an out-of-reactor environment. Prototypic light-water-reactor UO/sub 2/ fuel-pellet temperature profiles have been generated utilizing high flow rates (approximately 700 liters/min) of helium coolant gas, and a recirculating system has been fabricated to permit tests of up to 1000 h. Simulated light-water-reactor single- and multiple-thermal-cycle experiments will be conducted on both unclad and ceramic (fused silica) clad UO/sub 2/ pellet stacks. A laser dilatometer with a resolution of 1.27 x 10/sup -2/ mm (5 x 10/sup -4/ in.) is used to measure pellet dimensional increase continuously during thermal cycling. Acoustic emissions from thermal-gradient cracking have been detected and correlated with crack length and crack area. The acoustic emissions are monitored continuously to provide instantaneous information about thermal-gradient cracking. Posttest metallography and fracture-mechanics measurements are utilized to characterize cracking and crack healing.

A matrix of possible process steps is presented. Each process is evaluated by suitability criteria and categorized with respect to future usefulness. From the processes which have a high probability of incorporation into a future manufacturing factory, a possible process sequence is chosen. Studies of detailed cost analysis and factory projections have been initiated. Reliability considerations are discussed for module interconnections and encapsulant materials.

A measurement of the 6/sup 2/P/sub 1/2/ ..-->.. 7/sup 2/P/sub 1/2/ forbidden magnetic dipole matrix element in atomic thallium is described. A pulsed, linearly polarized dye laser tuned to the transition frequency is used to excite the thallium vapor from the 6/sup 2/P/sub 1/2/ ground state to the 7/sup 2/P/sub 1/2/ excited state. Interference between the magnetic dipole M1 amplitude and a static electric field induced E1 amplitude results in an atomic polarization of the 7/sup 2/P/sub 1/2/ state, and the subsequent circular polarization of 535 nm fluorescence. The circular polarization is seen to be proportional to (M1)/(E1) as expected, and measured for several transitions between hyperfine levels of the 6/sup 2/P/sub 1/2/ and 7/sup 2/P/sub 1/2/ states. The result is (M1) = -(2.11 +- 0.30) x 10/sup -5/ parallel bar e parallel bar dirac constant/2mc, in agreement with theory.

The manual supplements Regulatory Guide 8.15, ''Acceptable Programs for Respiratory Protection''. It provides broad guidance for the planned use of respirators to protect individuals from airborne radioactive materials that might be encountered during certain operations. The guidance is intended for use by management in establishing and supervising programs and by operating personnel in implementing programs. Guidance is primarily directed to the use of respirators to prevent the inhalation of airborne radioactive materials. Protection against other modes of intake (e.g., absorption, swallowing, wound injection) is, in general, not covered nor is the use of protective equipment for head, eye, or skin protection.

The theoretical and numerical data base development of the LARC-1 code is described. Four analytical models of fission product release from an HTGR core during the loss of forced circulation accident are developed. Effects of diffusion, adsorption and evaporation of the metallics and precursors are neglected in this first LARC model. Comparison of the analytic models indicates that the constant release-renormalized model is adequate to describe the processes involved. The numerical data base for release constants, temperature modeling, fission product release rates, coated fuel particle failure fraction and aged coated fuel particle failure fractions is discussed. Analytic fits and graphic displays for these data are given for the Ft. St. Vrain and GASSAR models.