This report presents the analysis of the LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step thermal transient. Previous analysis performed under subcontract by Basic Technology Incorporated was utilized where applicable. The SAASIII finite element computer program was used to determine stress distributions in the nozzles due to the step transient. Computer results were then incorporated in the necessary additional calculations to ascertain that stress limitations were not exceeded. The results of the analysis indicate that both the spray and surge nozzles will be within stress allowables prescribed by subsubarticle NB-3220 of the 1974 edition of the ASME Boiler and Pressure Vessel Code when subjected to currently known design, normal operating, upset, emergency, and faulted condition loads.

Under Contract 3772003 to the Lawrence Livermore Laboratory, Aerojet ElectroSystems Company has investigated a number of alignment system design topics for the NOVA and SHIVA upgrade lasers. Prior reports dealt with the Main Beam Alignment System, and with Multipass Amplifier Alignment Concepts. This report, which completes the contract, examines ways in which the Return Beam Diagnostic (RBD) package and Incident Beam Diagnostic (IBD) packages may be reconfigured to a more integrated package. In particular, the report shows that the RBD optics may be directly integrated in the Pointing Focus and Centering (PFC) sensor, and that the IBD optics may use the same basic common configuration as the PFC/RBD package.

A purchaser of industrial insulation is concerned with many factors which bear on the type of insulation selected. One of the most important factors, undoubtedly, is the thermal conductivity. The thermal conductivity is a measure of the ability of an insulation to conduct heat. The lower this value the better the insulation appears to the buyer. In the past it was generally assumed that the conductivity during the life of the insulation could be taken as a fixed property so long as external influences such as moisture or physical damage do not occur. Due to the dramatic increase in the cost and availability of energy in recent years, investigation of the validity of this long-standing assumption is in order. The purpose of this study was to determine whether deterioration of industrial insulation does occur and, if so, attempt to identify the reasons. In order to accomplish this, it was necessary to first develop methods by which the conductivity could be determined in the field. Once this was accomplished, a field test program was implemented. It was determined from this program that there was a significant difference between the conductivity values obtained and those which were expected from manufacturer's data. However, …

This is an interim report on the modifications which are being made to an existing sodium loop so that a new method of removing hydrogen from sodium can be evaluated in a flowing sodium system. Some preliminary results on the performance of this type of cold trap alternative in a static sodium system are reported. Some tentative reactor design parameters for this type of getter device are presented based on the static test results. The life of such a unit is calculated to be substantially greater than that of a cold trap of equal volume.

The design requirements, subsystem characteristics, environmental requirements, and cost and performance evaluation techniques are defined for the Line Focus Solar Central Power Systems. Specific passages revised are enumerated. (LEW)

Process automation continued in HH Building. Production of 7% /sup 38/Ar and 99.5% /sup 36/Ar, 128 g of 90+% /sup 13/C as elemental carbon, 445 g of 90+% /sup 13/C as methane, 3350 STP liters of 99.9% /sup 3/He and 100 STP liters of 99.9995% /sup 3/He, 99% /sup 86/Kr and 70% /sup 82/Kr, 100 liters of /sup 22/Ne, 0.4 STP liter of 40% /sup 124/Xe, 0.4 STP liter of 40% /sup 124/Xe, 0.3 STP liter of 5% /sup 124/Xe, 0.25 STP liter of 20% /sup 124/Xe, and 8.5 STP liters of 80% /sup 136/Xe were produced. A total of 23 grams of /sup 37/Cl, 20.9 mg of /sup 229/Th from aged UF/sub 4/, 47,359 mg of Th, and 4.2 g of /sup 234/U were also produced. Other research and production discussed includes: helium ionization potential, liquid thermal diffusion, molecular beam scattering, mutual diffusion coefficients of krypton-noble gas mixtures, NMR studies of metal hydrides, isotope effects of diffusion in vanadium hydride, EPR studies of hydrides, and theoretical studies of hydrogen in metals.

The decontamination work which has been accomplished is reviewed and it is concluded that it is worthwhile to investigate further four methods for decontamination for future demonstration. These are: dilute chemical; single stage strong chemical; redox processes; and redox/chemical in combination. Laboratory work is recommended to define the agents and processes for demonstration and to determine the effect of the solvents on PWR materials. The feasibility of Indian Point 1 for decontamination demonstrations is discussed, and it is shown that the system components of Indian Point 1 are well suited for use in demonstrations.

Various design parameters are evaluated that affect the performance of tritium-containment systems for fusion reactors. Our study included a review of such parameters as tritium forms, impurities, catalysts, adsorbents, getters, and as low as reasonably achievable principles. We organized these schemes, which can be considered for treating either air or inert atmospheres, so one could easily make orderly choices and tradeoffs for optimum performance. The relationships examined involved purification-system decontamination factors, flow rates, recycling and leakage, and environmental losses.

A stress analysis was performed on the 4''-IW-179-AB pipe system outside containment penetration S-5B. Deadweight, thermal expansion, and seismic loads were considered. The results indicate that this piping will meet ASME Section III, Class 2 requirements.

Line 2''-LS-120-AB outside containment penetration S-1A was analyzed to ASME Section III, Subsection NC (Class 2) criteria. The line is part of the LOFT Containment Isolation System. The model considered the line from the penetration outward through the second isolation valve. Results of the analysis show that this section of the line meets Class 2 requirements without modification.

An automated facility remotely and automatically analyzes soil, water, and sediment samples for uranium. The samples travel through pneumatic tubes and switches to be first irradiated by neutrons and then counted for resulting neutron and gamma emission. Samples are loaded into special carriers, or rabbits, which are then automatically loaded into the pneumatic transfer system. The sample carriers have been previously coded with an identification number, which can be automatically read in the system. This number is used for correlating and filing data about the samples. The transfer system, counters, and identification system are controlled by a network of microprocessors. A master microprocessor initiates routines in other microprocessors assigned to specific tasks. The software in the microprocessors is unique for this type of application and lends flexibility to the system.

Induced radioactivity in the blanket and other parts of a fusion reactor close to the plasma zone will dictate remote assembly, disassembly, and maintenance procedures. Time will be of the essence in these procedures. They must be practicable and certain. This paper discusses the reduction of a complicated Tokamak reactor to a simpler assembly via the use of a vacuum building in which to house the reactor and the introduction in this new model of cassette blanket modules. The cassettes significantly simplify remote handling.

MAGIC, a new one-dimensional particle code, simulates magneto-inductive phenomena in a cylindrically-symmetric magnetized plasma. We describe the physical model and the computational algorithm used for the code. A user's guide to and a listing of MAGIC are also included.

Gamma-ray spectrometric methods using high-resolution Ge(Li) and high purity Ge detectors have been used to quantify the concentrations and external exposure rates of radionuclides in the soil. These in situ methods have been used to study radionuclide deposition around nuclear power stations, the distribution of radionuclides at the Nevada Test Site, biogeochemical cycling of radionuclides, and the fate and impact of fallout radionuclides. Portable gamma-ray spectrometer systems used for various kinds of in situ field measurements include: large-volume coaxial Ge(Li) detectors for terrestrial gamma-ray surveys at several sites including preoperational nuclear power plants and for real-time measurements of nuclear reactor plume isotopic exposure rates; and planar, high purity Ge detectors for mapping /sup 241/Am and /sup 239/Pu soil concentrations, particularly at the Nevada Test Site. These applications are discussed along with a brief description of the methodology and techniques associated with in situ gamma-ray spectrometry.

Cost studies were done for Total Flow, double flash, and multistage flash binary systems for electric Energy production from the Salton Sea Geothermal Resource. The purpose was to provide the Department of energy's Division of Geothermal Energy with information by which to judge whether to continue development of the Total Flow system. Results indicate that the Total Flow and double flash systems have capital costs of $1,135 and $1,026 /kW with energy costs of 40.9 and 39.7 mills/kW h respectively. The Total Flow and double flash systems are not distinguishable on a cost basis alone; the multistage flash binary system, with capital cost of $1,343 /kW and energy cost of 46.9 mills/kW h, is significantly more expensive. If oil savings are considered in the total analysis, the Total Flow system could save 30% more oil than the double flash system, $3.5 billion at 1978 oil prices.

Delays in the start-up of the RefCOM facility in Pompano Beach, Florida, are outlined. The most serious delays involved problems with the screw conveyors. After many modifications had proven futile, it was decided that they were not applicable to the system and the screw conveyors were replaced with a rotary feeder. An itemized, chronological list of all plant modifications including the cost of labor and materials are presented in this report. Diagrams and daily work sheets are included. (DMC)

The conceptual design of a 40 to 50 MW closed cycle ammonia OTEC commercial plant, the preliminary design of a 10 MW OTEC module analogous to the 50 MW module, and the preliminary design of heat exchanger test articles (evaporator and condenser) representative of the 50 MW heat exchangers for testing in OTEC-1 are presented. This volume of the report includes the following appendices: H) conceptual design description of the electrical systems; I) control and instrumentation; J) OTEC power module assembly; and K) cost estimates for each of the cost components. (WHK)

The 24'' H and V Duct and related piping outside the LOFT containment and connected to containment penetration S-12A were analyzed to ASME Section III, Subsection NC (Class 2) criteria. The duct is part of the Containment Isolation System. The model considered the duct from the containment O.D. outward through the second isolation valve. Results of this analysis show that this section of the line will meet Class 2 requirements without modification.

Stress corrosion tests were conducted on 316 VIM/VAR stainless steel as part of the Tritium Facility's Quality Assurance Program. Initial results under severe conditions indicate earlier-than-expected failure. We are expanding our tests to further examine this problem.

The vaporization behavior of the Zr--Nb--O system was studied by means of successive vaporization, Knudsen effusion-target collection experiments, and mass spectrometric analysis of the vapors effusing from a Knudsen crucible. The successive vaporization experiments were performed on two ternary samples in open crucibles. X-ray powder diffraction patterns of the residues and x-ray fluorescence analysis of the condensates and residues indicated the preferential vaporization of niobium-containing species with the composition of the residue subsequently becoming closer to that of congruently vaporizing ZrO/sub 2-x/. The Knudsen effusion-target collection experiments were employed on two samples, pure NbO/sub 2/(s) and a two-phase ZrO/sub 2/--NbO/sub 2/ mixture, in order to obtain information on the activity of NbO/sub 2/ in the two-phase mixture. Second law enthalpies and entropies of sublimation as well as third law enthalpies were obtained for both systems. The vaporization behaviors of five compositions in the Zr--Nb--O system, NbO/sub 2/, NbO, a ZrO/sub 2/--NbO/sub 2/ two-phase mixture, Nb/sub 2/O/sub 5/, and Zr/sub 6/Nb/sub 2/O/sub 17/, were investigated. Above Nb/sub 2/O/sub 5/ and the fully oxidized Zr/sub 6/Nb/sub 2/O/sub 17/ oxygen is preferentially lost; over NbO/sub 2/, the two-phase ZrO/sub 2/--NbO/sub 2/ system, and NbO the principal gaseous species is NbO/sub 2/.

Quartz sand derived from alluvial fans that drain different lithologies at the Nevada Test Site can be distinguished on the basis of grain shape as described by the Fourier series in closed form. Specifically, we examined tuff units from the Piapi Canyon and Indian Trail Formations as well as carbonate-bearing clastic units from the Eleana Formation. Discrimiation between rock types was accomplished by examining the mean harmonic amplitude spectra and the grain shape frequency distributions at those harmonics that exhibit significant chi-square values. The results of these analyses indicate that the tuffs can be easily distinguished from the clastics. However, differences between samples from genetically similar rock types are not as prominent. Grain shape frequency distributions of tuffs and clastics show such strong differences that they can be characterized by standardized distributions. By comparing the shape frequency distributions of mixed sediment samples, it is possible to determine the relative contribution of tuff and clastics to any sediment sample taken within the drainage network. The Piapi Canyon, Indian Trail, and Eleana Formations have produced the thick alluvium sequence in the Rainier Mesa region of Yucca Flat. We believe it is likely that these grain shape relationships can also be applied to …

The LOFT pressurizer self-actuating safety-relief valves are constructed to the present state-of-the-art and should have reliability equivalent to the valves in use on PWR plants in the U.S. There have been no NRC incident reports on valve failures to lift that would challenge the Technical Specification Safety Limit. Fourteen valves have been reported as lifting a few percentage points outside the +-1% Tech. Spec. surveillance tolerance (9 valves tested over and 5 valves tested under specification). There have been no incident reports on failures to reseat. The LOFT surveillance program for assuring reliability is equivalent to nuclear industry practice.

Four unique deisgn features are described which make the Fast Flux Test Facility eminently suitable for irradiation test programs. These features are a fast flux level of 7 x 10/sup 15/ neutrons/cm/sup 2//sec, a 36-inch reference (breeder reactor) core height, test volumes suitable for testing of statistical quantities of materials, and the capability for direct (contact) or indirect (proximity) instrumentation of active core experiments.

Reliable performance of fuels for the Fast Flux Test Facility (FFTF) is of paramount importance for the FFTF program. Improved inspection techniques and processes are essential for controlling the quality of such fuels. Several considerations necessitated the development and application of improved inspection techniques and processes. These include fuel design, throughput rate, and pre-irradiation characterization requirements. Some of the more significant advances are in the areas of fuel pellet dimensional and weight measurements, fuel pin diameter measurements, and on-line, computerized quality status tracking. Advances in each of these areas are discussed.