This report describes a three-dimensional nonlinear TRANAL finite element analysis of a nuclear reactor subjected to ground shaking from a buried 50 kg explosive source. The analysis is a pretest simulation of a test event which was scheduled to be conducted in West Germany on 3 November 1979.

This report outlines the detailed design and system analysis of a solar industrial process steam system for the Lone Star Brewery. The industrial plant has an average natural gas usage of 12.7 MMcf per month. The majority of this energy goes to producing process steam of 125 psi and 353/sup 0/F at about 50,000 lb/h, with this load dropping to about 6000 lb/h on the weekends. The maximum steam production of the solar energy system is about 1700 lb/h. The climatic conditions at the industrial site give 50% of the possible amount of sunshine during the winter months and more than 70% during the summer months. The long-term yearly average daily total radiation on a horizontal surface is 1574 Btu/day-ft/sup 2/, the long-term yearly average daytime ambient temperature is 72/sup 0/F, and the percentage of clear day insolation received on the average day of the year is 62%. The solar steam system will consist of 9450 ft/sup 2/ of Solar Kinetics T-700 collectors arranged in fifteen 90-ft long rows through which 67.5 gpm of Therminol T-55 is pumped. This hot Therminol then transfers the heat collected to a Patterson-Kelley Series 380 unfired steam boiler. The solar-produced steam is then metered …

Two solar collectors using a pebble bed design were constructed and tested using air as the heat exchange media. One collector had pebbles of metallurgical grade coke, and the other had a frothy volcanic material called scoria. The highly irregular surface of such vesicular material should increase the path distance for the air and the surface exposed cavities should give some honeycomb effect. Both should yield greater efficiency. Actual testing shows the efficiencies to be comparable with other air collectors. Thus the advantages of the pebble bed lie in the availability of the bed material, its thermal and radiation stability, and its shielding of underlying collector materials from ultraviolet radiation. Several pebble bed collectors using water as the heat exchange media were constructed. However, basic problems prevented effective testing, and it is concluded that pebble bed collectors using water are impractical.

The effect of introducing a neutron and gamma shield into the annulus between the reactor vessel and the shield tank is analyzed. This addition has been proposed in order to intercept neutron streaming up the annulus during nuclear operations. Its installation will require removal of approximately 20-/sup 1///sub 2/ inches of stainless steel foil insulation at the top of the annulus. The resulting conduction path is believed to result in increased water temperatures within the shield tank, possibly beyond the 150/sup 0/F limit, and/or cooling of the reactor vessel nozzles such that adverse thermal stresses would be generated. A two dimensional thermal analysis using the finite element code COUPLE/MOD2 was done for the shield tank system illustrated in the figure (1). The reactor was assumed to be at full power, 55 MW (th), with a loop flow rate of 2.15 x 10/sup 6/ lbm/hr (268.4 kg/s) at 2250 psi (15.51 MPa). Calculations indicate a steady state shield tank water temperature of 140/sup 0/F (60/sup 0/C). This is below the 150/sup 0/F (65.56/sup 0/C) limit. Also, no significant changes in thermal gradients within the nozzle or reactor vessel wall are generated. A spacer between the gamma shield and the shield tank …

The project conceptual design activities are divided into six parts: Industrial Plant, Conceptual System Design, Collector Selection, Heat Transfer Fluid Selection, Site Fabrication, and Engineered Equipment. Included is an overview of the solar steam system and a brief discussion on the environmental impact of the project as well as the safety considerations of the system design. The effect of the solar system on the environment is negligible, and the safety analysis of the system indicates the considerations to be taken to minimize any potential safety hazard due to contamination of the food product or to fire. Both of these potential hazards are discussed in detail. Both the question of product contamination and the question of potential fire hazards will be presented to the industrial partner's safety committee so that the selection of the heat transfer fluid meets with their approval.

TRW is designing a system for the demonstration of the Solar Production of Industrial Process Steam. Included, besides the Conceptual Design, is an Environmental Impact Assessment and a System Safety Analysis report. The system as proposed and conceptualized consists of an array of 9520 square feet of parabolic trough concentrating solar energy collectors which generate pressurized hot water. The pressurized water is allowed to flash to steam at 300 psi (417/sup 0/F) and fed directly into the high pressure steam lines of the Ore-Ida Foods, Inc., processing plant in Ontario, Oregon. Steam is normally generated in the factory by fossil-fired boilers and is used by means of a steam-to-oil heat exchanger for the process of frying potatoes in their frozen food processing line. The high pressure steam is also cascaded down to 125 psi for use in other food processing operations. This solar system will generate 2 x 10/sup 6/ Btu/hr during peak periods of insolation. Steam requirements in the plant for frying potatoes are: 43 x 10/sup 6/ Btu/hr at 300 psi and 52 x 10/sup 6/ Btu/hr at the lower temperatures and pressures. The Ontario plant operates on a 24 hr/day schedule six days a week during the …

The present study indicates that the estimation of the gamma-ray strength function is the approach least subject to error when unmeasured capture cross sections are to be computed. An estimate is given for the /sup 88/..gamma..(n,..gamma..) cross section.

Measurements of neutron capture and total cross sections for /sup 186/Os, /sup 187/Os, and /sup 188/Os, neutron inelastic scattering cross sections for /sup 187/Os and /sup 238/U, and total cross sections for /sup 32/S + n are reported. This report is administrative in nature, with few data. 7 figures. (RWR)

The objective of the work reported here was to develop a model which could be used to assess the economic effects of energy-conservative technological innovations upon the pipeline industry. The model is a dynamic simulator which accepts inputs of two classes: the physical description (design parameters, fluid properties, and financial structures) of the system to be studied, and the postulated market (throughput and price) projection. The model consists of time-independent submodels: the fluidics model which simulates the physical behavior of the system, and the financial model which operates upon the output of the fluidics model to calculate the economics outputs. Any of a number of existing fluidics models can be used in addition to that developed as a part of this study. The financial model, known as the Systems, Science and Software (S/sup 3/) Financial Projection Model, contains user options whereby pipeline-peculiar characteristics can be removed and/or modified, so that the model can be applied to virtually any kind of business enterprise. The several dozen outputs are of two classes: the energetics and the economics. The energetics outputs of primary interest are the energy intensity, also called unit energy consumption, and the total energy consumed. The primary economics outputs are …

The sensitivity of mechanical and hydraulic snubber parameters to system displacements, stresses, and forces are analyzed. Acceleration threshold, clearance, and friction are evaluated for mechanical snubbers while hydraulic snubber investigations include lock velocity, bleed rate, unlock loading, clearance, and friction. The back-up structure is influential for both types of snubbers and although not a snubber parameter, per se, is treated like a parameter. Forcing functions are utilized, and include both harmonic and time history seismic inputs to the mathematical models. Mathematical models are used to simulate snubber characteristics. Special mathematical techniques are developed for economical use in piping programs. Acceptable parameter ranges are established, based on criteria for the various mechanical and hydraulic snubber characteristics.

On March 13, 1979, a plutonium oxide storage can ruptured in the 303-C storage facility, which is in the 300 Area of the Hanford Site, Washington. The facility is operated by the Pacific Northwest Laboratory (PNL); three PNL staff members were performing the storage operation. No injuries to these staff members resulted from the occurrence. A Class C Investigation Committee was appointed on March 14, 1979, by the Director, PNL. Subsequently, when the loss estimates became available, the Manager, Department of Energy-Richland Operations Office (DOE-RL), appointed a Class B Investigation Committee in accordance with DOE Manual Chapter 0502. As requested by DOE-RL, the Committee investigated technical elements of the causal sequence and management systems that should have or could have prevented the occurrence. The investigation included: review of the use of the 303-C facilities and the transfer containers; interviews with the involved personnel and their managers; analysis of technical studies related to involved materials and procedures; review of safe operating procedures, radiation work procedures, and transfer requirements applicable to the occurrence; and use of the Management Oversight and Risk Tree (MORT) and the Events and Causal Factors Charting methods. 15 figs.

Burzet is a proposed intermediate-yield underground test of a nuclear explosive at the Nevada Test Site. The possible existence of a high Paleozoic scarp and fault within 100 m of the proposed working point created concern as to their effect on the containment of the radioactive gases. A calculation of the expected stress wave interaction at the scarp and fault demonstrates that the effects are negligible. Results of the calculation are those expected from an event in a homogeneous media and are thus consistent with good containment experience on numerous previous detonations of similar yield, depth of burial, and medium properties.

In response to additional needs developed during a review of the LOFT Technical Specifications, two more pressure reduction and decontamination sump volume vs. initial temperature data points were calculated in order to adequately quench steam generator relief blowdown. The two additional points chosen were for 10,000 gallons (based on ECC requirements) and for 120/sup 0/F (NPSH limit maximum temperature). The results are that for 10,000 gallons in the sump the maximum initial temperature is 110/sup 0/F and for 120/sup 0/F initial temperature, a volume of 14,000 gallons is required in the sump. Calculations are shown on page two of this report. The maximum final PR and DS temperature was set at 140/sup 0/F to preclude the vibrational effects discussed in LTR 115-9 and its referenced operational experience reports.

The Rio Blanco Massive Hydraulic Fracturing Project was fielded in 1974 as a joint Industry/ERDA demonstration to test the relative effectiveness of MHF in the same formations that were stimulated by the Rio Blanco nuclear fracturing experiment. The project is essentially a companion effort to and a continuation of the preceding nuclear stimulation project, which took place in May, 1973. The well was fractured a total of four times, twice in the Upper Mesaverde and twice in the Fort Union. A fifth zone in the Upper Mesaverde was extensively tested but abandoned as being of insufficient quality for fracturing. In the four treatments, none appears to have fractured laterally as designed. In the Fort Union and Mesaverde each well must produce from numerous sand lenses, the lateral extent of which appears to be limited.

Numerical methods and computer programs are given to evaluate, for an arbitrary intermolecular potential, the classical transport collision integrals which appear in the kinetic theory of dilute gases. The method of Gaussian quadrature was employed to integrate the triple integral. A detailed discussion is given of the mathematics necessary to determine the boundaries of the individual integrations as well as a detailed analysis of errors introduced by the numerical procedures. Results for a recently published helium potential, the HFDHE2, are given. 5 references.

The intent of this study is to: (1) make a preliminary assessment of the accuracy and precision of insolation data with respect to user requirements, and (2) make a corresponding assessment of the minimum/maximum geographic network coverage. In order to make these preliminary assessments, several specific questions have been addressed. Specifically: (1) how should users of solar radiation be classified and what principal uses of the data are made by each class, (2) what temporal and spatial properties of the data network are required to adequately serve the defined uses and users of solar radiation data, (3) to what degree does the existing network and associated data fulfill the desired data system properties, and (4) what criteria should be applied in identifying and evaluating expanded network/data options. The findings and conclusions of investigation of these questions are presented.

The objective of this project was to evaluate and characterize the effects of various forging parameters on the metallographic structure and mechanical properties of 304L stainless steel forgings. Upset and die forgings were produced by hammer and Dynapak forging with forging temperatures ranging from 760 to 1145/sup 0/C, upset reductions ranging from 20 to 60%, and annealing times ranging from 0 to 25 minutes at 843/sup 0/C. The carbide precipitation behavior observed was found to be a function of forging temperature and annealing time. Higher forging temperatures were beneficial in avoiding continuous carbide precipitation and annealing at 843/sup 0/C promoted increased carbide precipitation. The yield strength of the unannealed forgings decreased with increasing forging temperature and, with the exception of the 1145/sup 0/C upset forgings, was significantly lowered by annealing.

A detailed description of the status of the design, fabrication, and testing of the Selenide Isotope Generator for the Galileo program is presented. (WHK)

TERA Corporation presents the results of a detailed seismic risk analysis of the Battelle Memorial Institute's Nuclear Research Facility at West Jefferson, Ohio. This report focuses on earthquakes.

A summary of measured data collected by numerous agencies cooperating in the Piledriver event, is presented together with calculations based on empirical relations deduced from past events in comparable media. Of 9 relations that have been proposed to predict cavity radius, 5 result in radii accurate to <3.5%. The remainder are off by about 10 to 18%. Three postshot recovered cores (U-15.01 PS-1, -2, -3) were examined on a gross scale prior to extensive detailed sampling for laboratory tests. The positions of injected glass seams, radioactivity, and shear zones were recorded. The orientation of several thousand core fractures was measured with respect to the core axes and distance from the shot point. Taking all observations into account, phenomena related to failure of rock is the Piledriver event are closely related to pre-existing weaknesses and inhomogeneities. (Longer abstract available)

Conceptual design studies of the target chamber defined the general configuration and dimensions of the chamber and the inlet plenum, orifice plate, and nozzle plate concepts required to generate the desired lithium jet fall. Preliminary studies were performed of the target chamber interfaces with the liquid lithium supply system, the laser system, the pellet injection system, and the target chamber mounting and support system. Target chamber environmental effects resulting from typical thermonuclear burns were evaluated. The outlet region of the target chamber was outlined conceptually, and preliminary design considerations were given to the annular graphite reflector regions of the target chamber and the associated liquid lithium coolant passages. (MOW)

The research performed was designed to identify spatial or temporal variation of any atmospheric parameters that might affect the operation of devices utilizing solar energy in the metropolitan Phoenix area. The first part of the research involved the analysis of all available solar and climatic data to determine their validity and comparability. For the standard climatic parameters, few difficulties were encountered, but the task of determining comparability of solar radiation data involved many pitfalls. It was concluded that most of the solar data acquired before January 1977 could not be used for purposes of identifying spatial variability. And, a year and a half of data does not represent a long enough period of time upon which to base sound conclusions about spatial and temporal variability of solar radiation in the metropolitan Phoenix region. The data currently available to us do not indicate any great variation of solar radiation in the metropolitan Phoenix area. However, any meaningful statements about spatial and temporal variability of solar radiation in the metropolitan Phoenix area must await the acquisition of additional data from well-calibrated equipment.

Proposals to amend Appendix A of Part 440 of Weatherization Assistance for Low-Income Persons are described. The proposals establish new specifications for the materials purchased for utilization in the weatherization of dwellings which qualify for assistance under Part 440. These proposed regulations prescribe the minimum requirements which must be met or exceeded by each type of material and the Federal standards to which they must conform. In addition, these regulations include installation requirements for each class of material installed at the request of the enduser. (MCW)

This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years.