Risk Management is the optimization of safety programs. This requires a formal systems approach to hazards identification, risk quantification, and resource allocation/risk acceptance as opposed to case-by-case decisions. The Management Oversight and Risk Tree (MORT) has gained wide acceptance as a comprehensive formal systems approach covering all aspects of risk management. It (MORT) is a comprehensive analytical procedure that provides a disciplined method for determining the causes and contributing factors of major accidents. Alternatively, it serves as a tool to evaluate the quality of an existing safety system. While similar in many respects to fault tree analysis, MORT is more generalized and presents over 1500 specific elements of an ideal ''universal'' management program for optimizing occupational safety.

The performance of any injector contemplated to replace the electrostatic tandem accelerators some time in the future should evidently match or surpass the characteristics of the tandems. It is a fortunate coincidence that the performance of the BNL tandem satisfies in most respects the requirements of the proposed collider, although originally tandems were not built with this application in mind. Requests for heavy ion beams with parameters suitable for injection into the rings of a heavy ion collider have appeared rather recently, at a stage when the high charge state ion sources, which in principle are capable of producing many ion species, have not yet reached such a level of performance. Therefore, consideration of such sources as part of a future injector replacing the tandem accelerators will have to rely on the extrapolation of results from existing models, developed for a different purpose. At the same time, present and future collider requirements for heavy ion beams should serve as a stimulus for the development of sources producing ions with adequate charge states and intensities. Injectors based on such sources may present a better alternative than the tandem accelerators because a higher charge-to-mass ratio of ions from the source results in …

The charge of this group was to evaluate the physics that can be done with a high luminosity {mu} scattering experiment at FNAL using the upgraded Tevatron muon beam, and consider the apparatus required. In this report, the physics that can be accomplished with a high luminosity {mu} scattering experiment is evaluated. The CERN and FNAL {mu} beams are compared in the context of such an experiment. The expected muon flux with the upgraded machine is estimated. Two possible detectors are compared: the air-core toroid experiment proposed by Guyot et al., and an upgraded version of the E665 double-diode apparatus now in place at FNAL. The relative costs of the detectors are considered. A list of detailed questions that need to be answered regarding the double-diode experiment has be compiled. 2 refs., 10 figs., 2 tabs.

This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previously used CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projections, dose accumulation by a number of pathways including food and water ingestion, early and latent health effects, and economic costs. The MACCS code can be used for a variety of applications. These include (1) probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, (2) sensitivity studies to gain a better understanding of the parameters important to PRA, and (3) cost-benefit analysis. This report is composed of three volumes. Volume I, the User's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems. Volume II, the Model Description, describes the underlying models that are implemented in the code, and Volume III, the Programmer's Reference Manual, describes the code's structure and database management.

The three boxes being reviewed all operate at a pressure of less than 15 psig. Since they are relieved at 13 psig, they fall outside the scopes of the ASME Pressure Vessel Code, Fermilab Engineering Standard SD-37B, and Chapter 5031 of the Fermilab Safety Manual, therefore a Pressure Vessel Engineering Note showing compliance with SD-37B is not required. In calculating the design stresses, only the largest of the three boxes, the signal board feed-thru box, was analyzed. This box had the largest spans and areas and would experience the largest pressure-related forces. The thinnest walls of each box were found to be in the top plates and they were also the side of the box which exposed the largest amount of area to internal pressure. The signal board feed-thru box top plate had at least twice the pressure area than either the instrumentation or hi-voltage boxes' top plates. This large disparity overshadows the slight difference in top plate thicknesses between the three boxes (0.56-inch vs. 0.25-inch and 0.3125-inch, respectively). Therefore, we felt the analysis of the larger signal board feedthru box would justify the design of the smaller instrumentation and hi-voltage boxes. Appended to the end of this engineering note …

This report describes the MACCS computer code. The purpose of this code is to simulate the impact of severe accidents at nuclear power plants on the surrounding environment. MACCS has been developed for the US Nuclear Regulatory Commission to replace the previously used CRAC2 code, and it incorporates many improvements in modeling flexibility in comparison to CRAC2. The principal phenomena considered in MACCS are atmospheric transport, mitigative actions based on dose projection, dose accumulation by a number of pathways including food and water ingestion, early and latent health effects, and economic costs. The MACCS code can be used for a variety of applications. These include (1) probabilistic risk assessment (PRA) of nuclear power plants and other nuclear facilities, (2) sensitivity studies to gain a better understanding of the parameters important to PRA, and (3) cost-benefit analysis. This report is composed of three volumes. Volume I, the User's Guide, describes the input data requirements of the MACCS code and provides directions for its use as illustrated by three sample problems. Volume II, the Model Description, describes the underlying models that are implemented in the code, and Volume III, the Programmer's Reference Manual, describes the code's structure and database management. 59 refs., …

A comprehensive theoretical study has been carried out on the flow behavior of both single and multiple phase non-Newtonian fluids in porous media. This work is divided into three parts: development of numerical and analytical solutions; theoretical studies of transient flow of non-Newtonian fluids in porous media; and applications of well test analysis and displacement efficiency evaluation to field problems. A fully implicit, integral finite difference model has been developed for simulation of non-Newtonian and Newtonian fluid flow through porous media. Several commonly-used rheological models of power-law and Bingham plastic non-Newtonian fluids have been incorporated in the simulator. A Buckley-Leverett type analytical solution for one-dimensional, immiscible displacement involving non-Newtonian fluids in porous media has been developed. An integral method is also presented for the study of transient flow of Bingham fluids in porous media. In addition, two well test analysis methods have been developed for analyzing pressure transient tests of power-law and Bingham fluids, respectively. Applications are included to demonstrate this new technology. The physical mechanisms involved in immiscible displacement with non-Newtonian fluids in porous media have been studied using the Buckley-Leverett type analytical solution. In another study, an idealized fracture model has been used to obtain some insights into …

This concerns the transmittal of the Complete Quick Plot Set for Test 867{underscore}13, 90% OSV Power Best Estimate LOCA at 80 F, SRP-1,038. Attached for your information is the subject plot set containing data plots for the complete test spanning from about {minus}330 to 70 seconds, time scale enhancements at {minus}1 to 5 seconds, and a few custom plots. Unlike the previous tests, the power supply safety trips were returned to their ``non-recovery`` values with a 30% post-LOCA nominal flow reduction trip and 400 F metal temperature trips on the HP oscillograph and METRAscope. A couple of observations are noted comparing this test to its predecessor, Test 867{underscore}08.

This volume contains appendices D6 through D8 containing laboratory test data: from MK-F investigation, 1987, Old Rifle and New Rifle sites; on bentonite amended radon barrier material; and from MK-F investigation, 1987, riprap tests.

The primary objective of this work is the development of a comprehensive numerical model describing the time evolution of fouling under realistic heat exchanger conditions. As fouling is a complex interaction of gas flow, mineral transport and adhesion mechanisms, understanding and subsequently improved controlling of fouling achieved via appropriate manipulation of the various coupled, nonlinear processes in a complex fluid mechanics environment will undoubtedly help reduce the substantial operating costs incurred by the utilities annually, as well as afford greater flexibility in coal selection and reduce the emission of various pollutants. In a more specialized context the numerical model to be developed as part of this activity will be used as a tool to address the interaction of the various mechanisms controlling deposit development in specific regimes or correlative relationships. These should prove of direct use to the coal burning industry.

Methods of preparation of the copper, cobalt, and titanium catalysts were outlined. The catalyst samples were then analyzed through nuclear magnetic and nuclear quadrupole resonance.

On the subject of the transmittal of the Complete Quick Plot Set for Test 867{underscore}30, 4.75 MW Hard Pressure Transient LOCA at 80 F, SRP-1,141: Attached for your information is the subject plot set containing data plots for the complete test spanning from about {minus}320 to 90 seconds, time scale enhancements at {minus}1 to 5 seconds and a few custom plots. The time scale is set up so that 0 seconds corresponds to the start of the LOCA transient. The power supply safety temperature trips for the METRAscope and HP oscillograph were set a 400 F, consistent with previous tests. Flow trip setpoints (total flow from the venturi (IPD04) and channel pitot measurements) were configured for a power trip at an 80% reduction in flow from the post-LOCA expected flow value.

Independent testing of the UNSAT-H computer code, Version 2.0, was conducted to establish confidence that the code is ready for general use in performance assessment applications. Verification and benchmark test problems were used to check the correctness of the FORTRAN coding, computational efficiency and accuracy of the numerical algorithm, and code, capability to simulate diverse hydrologic conditions. This testing was performed using a structured and quantitative evaluation protocol. The protocol consisted of: blind testing, independent applications, maintaining test equivalence and use of graduated test cases. Graphical comparisons and calculation of the relative root mean square (RRMS) values were used as indicators of accuracy and consistency levels. Four specific ranges of RRMS values were chosen for in judging the quality of the comparison. Four verification test problems were used to check the computational accuracy of UNSAT-H in solving the uncoupled fluid flow and heat transport equations. Five benchmark test problems, ranging in complexity, were used to check the code`s simulation capability. Some of the benchmark test cases include comparisons with laboratory and field data. The primary findings of this independent testing is that the UNSAT-H is fully operationaL In general, the test results showed that computer code produced unsaturated flow simulations …

To forecast the ecological impact of global change, research initiatives are needed on the explicit role of humans in ecological systems, and on how ecological processes functioning at different spatial and temporal scales are coupled. Furthermore, to synthesize the results of ecological research for Congress, policymakers, and the general public, a new agency, called the United States Ecological Survey (USES) is urgently required. Also, a national commitment to environmental health, as exemplified by establishing a National Institutes of the Environment (NIE), should be a goal.

Dynamic Monte Carlo simulations were performed to obtain the dynamic scaling behavior of isolated, self-avoiding chains below the theta temperature. Simulations were conducted using both face-centered cubic and body-centered cubic lattice models, which use only one-bead elementary motions. Temperature effects were simulated by a nearest neighbor (square-well) interaction potential with a minimum energy {epsilon}. The relaxation times of the normal modes and the scaling exponents obtained are consistent with the predictions of Brochard and DeGennes for gel mode formation. The scaling exponent relating relaxation times to mode number showed high correlation with coil density. Dynamic scaling results were model independent for a given value of {mu}{phi} where {mu} is the coordination number minus one and {phi} = {minus} {epsilon}/k{sub B}T.

We present here the physics program planned for Hall A at CEBAF. It encompasses exclusive as well as inclusive electromagnetic measurements requiring both high precision and accuracy.The program includes measurements of the elementary form factors of the nucleon, systematic studies of the few nucleon systems (d, 3,4He), high momentum structure of nuclei, their structure at high Q^2 to look for hadronization and quark effects, spin response of nuclei via (vector-e, e'vector-p) reactions and the study of nuclear pion fields.

A comprehensive generic component failure data base has been developed for light water and liquid sodium reactor probabilistic risk assessments (PRAs) . The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) and the Centralized Reliability Data Organization (CREDO) data bases were used to generate component failure rates . Using this approach, most of the failure rates are based on actual plant data rather than existing estimates .

As part of the Component Fragility Program which was initiated in FY 1985, three additional equipment classes have been evaluated. This report contains the fragility results and discussions on these equipment classes which are switchgear, I and C panels and relays. Both low and medium voltage switchgear assemblies have been considered and a separate fragility estimate for each type is provided. Test data on cabinets from the nuclear instrumentation/neutron monitoring system, plant/process protection system, solid state protective system and engineered safeguards test system comprise the BNL data base for I and C panels (NSSS). Fragility levels have been determined for various failure modes of switchgear and I C panels, and the deterministic results are presented in terms of test response spectra. In addition, the test data have been evaluated for estimating the respective probabilistic fragility levels which are expressed in terms of a median value, an uncertainty coefficient, a randomness coefficient and an HCLPF value. Due to a wide variation of relay design and the fragility level, a generic fragility level cannot be established for relays. 7 refs., 13 figs., 12 tabs.

In the fall of 1988 the Beam Position Monitor (BPM) Task Force recommended that linac BPM processors be pulled out of the linac, modified, adjusted for offsets, recalibrated, and reinstalled. As of the end of 1989 this process had been completed on all linac type BPM processors. This paper discusses these modifications and tests.

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Process verification testing using in situ vitrification (ISV) was successfully performed in a pilot-scale test using soils containing fuel oils and heavy metals from Site 10 Installation Restoration Program (IRP) at the Arnold Engineering Development Center (AEDC) located in the southern portion of middle Tennessee. This effort was directed through the U.S. Department of Energy ' s Hazardous Waste Remedial Action Program (HAZWRAP) Office managed by Martin Marietta Energy Systems. In situ vitrification is a thermal treatment process that converts contaminated soils and wastes into a durable product containing glass and crystalline phases. During processing, heavy metals or other inorganic constituents are retained and immobilized in the glass structure; organic constituents are typically destroyed or removed and captured by the off-gas treatment system. The objective of this test is to verify the applicability of the ISV process for stabilization of the contaminated soil at Site 10 . The pilotscale ISV testing results, reported herein, indicate that the AEDC Site 10 Fire Training Area may be successfully processed by ISV. Site 10 is a fire training pit that is contaminated with fuel oils and heavy metals from fire training exercises. Actual site material was processed by ISV to verify its feasible …

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A comprehensive theoretical study has been carried out on the flow behavior of both single and multiple phase non-Newtonian fluids in porous media. This work is divided into three parts: (1) development of numerical and analytical solutions; (2) theoretical studies of transient flow of non-Newtonian fluids in porous media; and (3) applications of well test analysis and displacement efficiency evaluation to field problems. A fully implicit, integral finite difference model has been developed for simulation of non-Newtonian and Newtonian fluid flow through porous media. Several commonly-used rheological models of power-law and Bingham plastic non-Newtonian fluids have been incorporated in the simulator. A Buckley-Leverett type analytical solution for one-dimensional, immiscible displacement involving non-Newtonian fluids in porous media has been developed. Based on this solution, a graphic approach for evaluating non-Newtonian displacement efficiency has been developed. The Buckley-Leverett-Welge theory is extended to flow problems with non-Newtonian fluids. An integral method is also presented for the study of transient flow of Bingham fluids in porous media. In addition, two well test analysis methods have been developed for analyzing pressure transient tests of power-law and Bingham fluids, respectively. Applications are included to demonstrate this new technology. The physical mechanisms involved in immiscible displacement with …

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