This report describes the CTCN computer code, designed to solve the equations of transient colloidal transport of radionuclides in porous and fractured media. This Fortran 77 package solves systems of coupled nonlinear differential equations with a wide range of boundary conditions. The package uses the Method of Lines technique with a special section which forms finite-difference discretizations in up to four spatial dimensions to automatically convert the system into a set of ordinary differential equations. The CTCN code then solves these equations using a robust, efficient ODE solver. Thus CTCN can be used to solve population balance equations along with the usual transport equations to model colloid transport processes or as a general problem solver to treat up to four-dimensional differential systems.

This report describes FLUFIX/MOD2, a computer program that was developed as a two-dimensional analytical tool, based on a two-fluid hydrodynamic model, for application to fluid-flow simulation in fluid-solids systems and replaces the Interim User`s Manual for FLUFIX/MOD1. The field equations that constitute the two-fluid model used in FLUFIX/MOD2 and the constitutive relationships required to close this system of equations, as well as the finite-difference equations that approximate these equations and their solution procedure, are presented and discussed. The global structure of FLUFIX/MOD2 that implements this solution procedure is discussed. The input data for FLUFIX/MOD2 are given, and a sample problem for a fluidized bed is described.

As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix, Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test, especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guidelines, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes.

This report discusses the following topics on the Soleoidal Detector Collaboration: Summary and overview of the detector; physics and detector requirements; central tracking system; superconducting magnet; calorimetry; muon system; electronics; online computing; offline computing; safety; experimental facilities; installation; test and calibration beam plan; and cost and schedule summary.

This report discusses the following topics on the Soleoidal Detector Collaboration: Summary and overview of the detector; physics and detector requirements; central tracking system; superconducting magnet; calorimetry; muon system; electronics; online computing; offline computing; safety; experimental facilities; installation; test and calibration beam plan; and cost and schedule summary.

This is the tenth technical progress report in connection with the Cooperative Agreement between DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the period of work completed during the First Quarter of C 1992. Work focused on supporting field construction activities and expediting delivery of equipment. The project is on schedule. The following significant events occurred during this report period: The major components of the system were delivered to the site and installed: contract Modification No. 5 issued to Westinghouse authorized partial funding for proof-of-concept touting of an alternate filter candle material at Karhula, Finland; and contract Modification No. 2, issued to Babcock & Wilcox covered additional material (hangers, steel) and certain work scope changes.

The technical progress achieved during the period 30 September 1911 through 29 March 1992 on Contract DE-AC03-91SF18852.000 Radioisotope Thermoelectric Generators and Ancillary Activities is described in this document. This report is organized by the program task structure as follows: spacecraft integration and liaison, engineering support, safety, qualified unicouple production, ETG fabrication, assembly and test, ground support equipment (GSE), RTG shipping and launch support, designs, reviews, and mission applications, project management, quality assurance, reliability, contract changes, and non-capital CAGO, and CAGO acquisition (Capital Funds).

Mixed and low-level wastes generated at the Idaho National Engineering Laboratory (INEL) are required to be managed according to applicable State and Federal regulations, and Department of Energy Orders that provide for the protection of human health and the environment. The Mixed and Low-Level Waste Treatment Facility Project was chartered in 1991, by the Department of Energy to provide treatment capability for these mixed and low-level waste streams. The first project task consisted of conducting engineering studies to identify the waste streams, their potential treatment strategies, and the requirements that would be imposed on the waste streams and the facilities used to process them. The engineering studies, initiated in July 1991, identified 37 mixed waste streams, and 55 low-level waste streams. This report documents the waste stream information and potential treatment strategies, as well as the regulatory requirements for the Department of Energy-owned treatment facility option. The total report comprises three volumes and two appendices. This report consists of Volume 1, which explains the overall program mission, the guiding assumptions for the engineering studies, and summarizes the waste stream and regulatory information, and Volume 2, the Waste Stream Technical Summary which, encompasses the studies conducted to identify the INEL`s waste …

The Seismic Record Processing Program (SRP) is an interactive computer code developed for the calculation of artificial earthquake records that comply with the US Nuclear Regulatory Commission Standard Review Plan. The basic objective of SRP is the calculation of artificial seismic time histories that correspond to Design Response Spectra specified in the US Atomic Energy Commission Regulatory Guide 1.60 and/or the Power Spectral Density (PSD) requirements of the NRC Standard Review Plan. However, SRP is a general computer code and can accommodate any arbitrarily specified Target Response Spectra (TRS) or PSD requirements. In addition, among its other futures, SRP performs quadratic baseline correction and calculates correlations factors for a set of up to three earthquake records. This manual is prepared in two parts. The first part describes the methodologies and criteria used while the second is a user`s manual. In section 1 of the first part, the techniques used for the adjustment of a given earthquake record to a required TRS family of curves for a set of specified damping ratios are presented. Similarly, in section 2 of the first part, the PSD of an earthquake record is compared to a target PSD and adjusted accordingly. Sections 3 and 4 …

A field of heliostats suffers losses caused by shading and blocking by neighboring heliostats. The complex geometry of multiple shading and blocking events suggests that a processing code is needed to update the boundary vector for each shading or blocking event. A new version, RSABS, (programmer's manual included) simulates the split-rectangular heliostat. Researchers concluded that the dominant error for the given heliostat geometry is caused by the departure from planarity of the neighboring heliostats. It is recommended that a version of the heliostat simulation be modified to include losses due to nonreflective structural margins, if they occur. Heliostat neighbors should be given true guidance rather than assumed to be parallel, and the resulting nonidentical quadrilateral images should be processed, as in HELIOS, by ignoring overlapping events, rare in optimized fields.

A field of heliostats suffers losses caused by shading and blocking by neighboring heliostats. The complex geometry of multiple shading and blocking events suggests that a processing code is needed to update the boundary vector for each shading or blocking event. A new version, RSABS, (programmer`s manual included) simulates the split-rectangular heliostat. Researchers concluded that the dominant error for the given heliostat geometry is caused by the departure from planarity of the neighboring heliostats. It is recommended that a version of the heliostat simulation be modified to include losses due to nonreflective structural margins, if they occur. Heliostat neighbors should be given true guidance rather than assumed to be parallel, and the resulting nonidentical quadrilateral images should be processed, as in HELIOS, by ignoring overlapping events, rare in optimized fields.

To enhance quality, an independent verification and validation (IV&V) review is conducted as software requirements are defined. Requirements are inspected for consistency and completeness. IV&V strives to detect defects early in the software development life cycle and to prevent problems before they occur. The IV&V review process of a massive software requirements specification, the Reserve Component Automation System (RCAS) Functional Description (FD) is explored. Analysis of the RCAS FD error history determined that there are no predictors of errors. The size of the FD mandates electronic analysis of the databases. Software which successfully performs automated consistency and completeness checks is discussed. The process of verifying the quality of analysis software is described. The use of intuitive ad hoc techniques, in addition to the automatic analysis of the databases, is required because of the varying content of the requirements databases. The ad hoc investigation process is discussed. Case studies are provided to illustrate how the process works. This thesis demonstrates that it is possible to perform an IV&V review on a massive software requirements specification. Automatic analysis enables inspecting for completeness and consistency. The work with the RCAS FD clearly indicates that the IV&V review process is not static; it must …

A system transient analysis computer model (HFIRSYS) has been developed for analysis of small break loss of coolant accidents (LOCA) and operational transients. The computer model is based on the Advanced Continuous Simulation Language (ACSL) that produces the FORTRAN code automatically and that provides integration routines such as the Gear`s stiff algorithm as well as enabling users with numerous practical tools for generating Eigen values, and providing debug outputs and graphics capabilities, etc. The HFIRSYS computer code is structured in the form of the Modular Modeling System (MMS) code. Component modules from MMS and in-house developed modules were both used to configure HFIRSYS. A description of the High Flux Isotope Reactor, theoretical bases for the modeled components of the system, and the verification and validation efforts are reported. The computer model performs satisfactorily including cases in which effects of structural elasticity on the system pressure is significant; however, its capabilities are limited to single phase flow. Because of the modular structure, the new component models from the Modular Modeling System can easily be added to HFIRSYS for analyzing their effects on system`s behavior. The computer model is a versatile tool for studying various system transients. The intent of this report …

To enhance quality, an independent verification and validation (IV V) review is conducted as software requirements are defined. Requirements are inspected for consistency and completeness. IV V strives to detect defects early in the software development life cycle and to prevent problems before they occur. The IV V review process of a massive software requirements specification, the Reserve Component Automation System (RCAS) Functional Description (FD) is explored. Analysis of the RCAS FD error history determined that there are no predictors of errors. The size of the FD mandates electronic analysis of the databases. Software which successfully performs automated consistency and completeness checks is discussed. The process of verifying the quality of analysis software is described. The use of intuitive ad hoc techniques, in addition to the automatic analysis of the databases, is required because of the varying content of the requirements databases. The ad hoc investigation process is discussed. Case studies are provided to illustrate how the process works. This thesis demonstrates that it is possible to perform an IV V review on a massive software requirements specification. Automatic analysis enables inspecting for completeness and consistency. The work with the RCAS FD clearly indicates that the IV V review process …

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process.

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process.

The Energy Division is one of 17 research divisions at Oak Ridge Laboratory. Its goals and accomplishments are described in this annual progress report for FY 1991. The division`s total expenditures in FY 1991 were $39.1 million. The work is supported by the US Department of Energy, US Department of Defense, many other federal agencies, and some private organizations. Disciplines of the 124 technical staff members include engineering, social sciences, physical and life sciences, and mathematics and statistics. The Energy Division`s programmatic activities focus on three major areas: (1) analysis and assessment, (2) energy conservation technologies, and (3) military transportation systems. Analysis and assessment activities cover energy and resource analysis, the preparation of environmental assessments and impact statements, research on waste management, analysis of emergency preparedness for natural and technological disasters, analysis of the energy and environmental needs of developing countries, technology transfer, and analysis of civilian transportation. Energy conservation technologies include electric power systems, building equipment (thermally activated heat pumps, advanced refrigeration systems, novel cycles), building envelopes (walls, foundations, roofs, attics, and materials), and technical issues for improving energy efficiency in existing buildings. Military transportation systems concentrate on research for sponsors within the US military on improving the efficiency …

The Energy Division is one of 17 research divisions at Oak Ridge Laboratory. Its goals and accomplishments are described in this annual progress report for FY 1991. The division's total expenditures in FY 1991 were $39.1 million. The work is supported by the US Department of Energy, US Department of Defense, many other federal agencies, and some private organizations. Disciplines of the 124 technical staff members include engineering, social sciences, physical and life sciences, and mathematics and statistics. The Energy Division's programmatic activities focus on three major areas: (1) analysis and assessment, (2) energy conservation technologies, and (3) military transportation systems. Analysis and assessment activities cover energy and resource analysis, the preparation of environmental assessments and impact statements, research on waste management, analysis of emergency preparedness for natural and technological disasters, analysis of the energy and environmental needs of developing countries, technology transfer, and analysis of civilian transportation. Energy conservation technologies include electric power systems, building equipment (thermally activated heat pumps, advanced refrigeration systems, novel cycles), building envelopes (walls, foundations, roofs, attics, and materials), and technical issues for improving energy efficiency in existing buildings. Military transportation systems concentrate on research for sponsors within the US military on improving the efficiency …

This paper documents the results of a sequence of tests conducted to evaluate the DoD Computer-aided Acquisition and Logistic Support (CALS) data interchange capability of the Air Force Engineering Data Computer-Assisted Retrieval System (EDCARS). The CALS initiative specifies a standard digital interface to streamline the interchange of technical data between the DoD and the commercial sector. The CALS Test Network (CTN) is tasked to conduct tests of military standards which specify this digital interface. The testing results outlined in this report are intended to evaluate the EDCARS systems`s ability to sport CALS data interchanges and establish the level of technical data interoperability implemented at this DoD engineering data repository.

K-Reactor`s number one GM diesel (GM-lK) suffered recurrent, premature piston pin bushing failures between July 1990 and January 1991. These failures raised a concern that the engine`s original design capabilities were being exceeded. Were we asking old engines to do too much by powering 1200 kw (continuous) rated electrical generators? Was excessive wear of the piston pin bushings a result of having exceeded the engine`s capabilities (overload), or were the recent failures a direct result of poor quality, poor design, or defective replacement parts? Considering the engine`s overall performance for the past 30 years, during which an engine failure of this nature had never occurred, and the fact that 1200 kw was approximately 50% of the engine`s original tested capability, Reactor Engineering did not consider it likely that an overloaded engine caused bushing failures. What seemed more plausible was that the engine`s failure to perform was caused by deficiencies in, or poor quality of, replacement parts.The following report documents: (1) the results of K-Reactor EDG failure analysis; (2) correlation of P- and C-Reactor GM diesel teardowns; (3) the engine rebuild to blueprint specification; (4) how the engine was determined ready for test; (5) testing parameters that were developed; (6) a …

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The remainder of this report provides a detailed, final status of Andersen Consulting`s participation in the FMS systems implementation project and offers suggestions for continued FMS improvements. The report presents the following topics of discussion: (1) Summary and Status of Work (2) Recommendations for Continued Success (3) Contract Deliverables and Client Satisfaction The Summary and Status of Work section presents a detailed, final status of the FMS project at the termination of Andersen`s full-time participation. This section discusses the status of each FMS sub-system and of the Andersen major project deliverables. The Recommendations section offers suggestions for continued FMS success. The topics discussed include recommendations for each of the following areas: (1) End User and Business Operations (2) AISD; Development and Computer Operations (3) Software (4) Technical Platform (5) Control Procedures The Contract Deliverables and Client Satisfaction section discusses feedback received from Johnson Controls management and FMS system users. The report also addresses Andersen`s observations from the feedback.

The essential elements of an international information exchange system on dose control at nuclear power plants are summarized. Information was collected from literature abstracting services, by attending technical meetings, by circulating data collection forms, and through personal contacts. Data are assembled in various databases and periodically disseminated to several hundred interested participants through a variety of publications and at technical meetings. Immediate on-line access to the data is available to participants with modems, commercially available communications software, and a password that is provided by the Brookhaven National Laboratory (BNL) ALARA Center to authorized users of the system. Since January 1992, rapid access also has been provided to persons with fax machines. Some information is available for ``polling`` the BNL system at any time, and other data can be installed for polling on request. Most information disseminated to data has been through publications; however, new protocols, simplified by the ALARA Center staff, and the convenience of fax machines are likely to make the earlier availability of information through these mechanisms increasingly important.

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