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 …

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)

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.

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 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.

Theoretical discussions on seismic design testing are presented under the following appendix headings: system functions, pulse optimization program, system identification, and motion response calculations from inertance measurements of a nuclear power plant.

Engineering and construction activities associated with the Dresden Unit 1 chemical cleaning facility are described for January to June 1979.

A neutron spectrometer that acquires and unfolds data in the field has been developed for use in the energy range from 1 to 20 MeV. The system includes an NE213 organic scintillation detector, automatic gain stabilization, automatically stabilized pulseshape discrimination, an LSl-11 microprocessor for control and data reduction, and a multichannel analyzer for data acquisition. The system, with the exception of the multichannel analyzer, is mounted in a suitcase 47 by 66 by 23.5 cm. The mass is 23.5 kg.

Milestone Report No. 1 was delivered on June 1, 1979 and related to the conversion of Units 1-4. Milestone Report No. 2 describes the conversion of Units 5-12 from direct contact condensers which use the iron-catalyst/peroxide/caustic systems to surface condensers and H{sub 2}S abatement with the Stretford Process Unit. This Report is a 10 week progress report that specifically addresses itself to the differences that are encountered between Units 5-6, 7-10 and 11-12. The task schedule shown in the Summary Section was originally presented to PG and E at the Project Kick-Off Meeting on Monday, April 23. Units 11 and 12 retrofit concept which appears in this report was evaluated with a two pass surface condenser running parallel to the turbine shaft. This concept requires the relocation of the turbine lube oil tank, instrument air compressor and battery storage rack facilities. On Wednesday, June 27, the condenser supplier notified Rogers Engineering that it was feasible to design and install a four pass, two tube bundle condenser at right angle condenser to the turbine-generator shaft. The four pass condenser concept will eliminate the need of relocating equipment sensitive to turbine operation. However, schedule requirements for Milestone Report No. 2 left no …

An extension of the methods of Lindhard et at. was used to calculate the total displacement function n/sub ij/(E) for a number of diatomic materials, where n/sub ij/(E) is defined to be the average number of atoms of type j which are displaced from their sites in a displacement cascade initiated by a PKA of type i and energy E. From the n/sub ij/(E) one can calculate the fraction n/sub ij/(E) of the displacements produced by a type i PKA with energy E which are of type j. Values of the n/sub ij/ for MgO, CaO, Al/sub 2/O/sub 3/, and TaO are presented. It is shown that for diatomic materials with mass ratios reasonably near one (e.g., MgO, Al/sub 2/O/sub 3/) and equal displacement thresholds for the two species the n/sub ij/ become independent of the PKA type i at energies only a few times threshold. However, for larger mass ratios the n/sub ij/ do not become independent of i until much larger, energies are reached - e.g. > 10/sup 5/ eV for TaO. In addition, it is found that the n/sub ij/ depend sensitively on the displacement thresholds, with very dramatic charges occuring when the two thresholds become significantly …

Thirty-one neutron cross sections have been extended to 44 MeV for dosimetry applications at high energy accelerator sources. Integral testing in Be(d,n) fields at E/sub d/ = 14, 16, and 40 MeV shows that 22 cross sections are accurate to within +- 10%. An example of routine flux-spectral unfolding and damage analysis is shown with an error analysis. Cross section needs are discussed.

Milestone Report No. 3 is a progress report. Rogers Engineering Co., Inc. has investigated what sites are best suited for consolidation of power generating units 1 through 12 for processing the noncondensable gases through the Stretford Process for H{sub 2}S abatement below 10% of the mass flow. The consolidation arrangement for the power generating units are Units 1 through 6 which produces 187 MWe power. Units 7-8 and 11 producing 212 MWe and Units 9-10 and 12 which also produces 212 MWe power. Site survey and selection for the Stretford units provided for a primary and alternative site for each consolidation. Each of these three groups of plants is associated with its Stretford Process Plant. The gas blowers located at each power plant to push the noncondensable gases through the stainless steel pipe network to the Stretford Process have been sized. When combining the new auxiliary load requirements of these blowers and the Stretford units it was determined that additional auxiliary transformer capacity is necessary. We are investigating additional alternatives with respect to the Stretford Process application. This data will be submitted in the Final Report, See Section 6.

TATB (1,3,5 - triamino 2,4,6 - Trinitrobenzene) is a very stable explosive that is remarkably insensitive to severe impact and thermal environment. Experiments on its initiation and detonation characteristics have found it difficult to initiate under the energy transfer of thin flyer plates accelerated by electrically exploded metal foils. Figure 1 shows the propagation of a detonation front in such an experiment. Generally, the detonation waves are confined in the region directly in front of the flyer impact surface, leaving a substantial portion of the HE undetonated. It has been suggested by Lawrence Livermore personnel that a preheated TATB charge may improve its sensitivity and thus reduce or eliminate this deficiency. The above experiments were performed at the sample temperatures ranging from -54{degrees} to +74{degrees}C. As the temperature was lowered while the flyer impact velocity remained the same, a pronounced increase in the curvature of the detonation front was observed. This results in a significant decrease in the divergence of the detonation wave. Although an accurate relationship between the wave front divergence and the sample temperature is not available, it is generally believed that, due to an accelerated rate of chemical reaction, the detonation will significantly improve at higher temperatures. …

One hundred MAD-1021 slapper test devices were built to fill the reimbursable order CM8-2909G-1 for W.F. Hemsing of Los Alamos Scientific Laboratory. Physical vapor deposition (PVD) techniques were successfully used to prepare the slapper foil assemblies. The 0. 381 mm square bridge foils were of aluminium 3 micrometers thick. Copper solder pads of 1.0 to 1.5 micrometer thickness were also applied using PVD techniques. A total of 120 were fabricated and submitted to the fabrication group for assembly. The 100 completed slapper units were fabricated with 0.025 mm thick Kapton flyers. Barrels for these slapper units were 0.38 mm long with a 0.42 mm diameter.

A battery of statistical techniques are combined to improve detection of low-level dose response. First, Mahalanobis distances are used to classify objects as normal or abnormal. Then the proportion classified abnormal is regressed on dose. Finally, a subset of regressor variables is selected which maximizes the slope of the dose response line. Use of the techniques is illustrated by application to mouse sperm damaged by low doses of x-rays.