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This is the final report on a project to support a science/mathematics summer program aimed at minority middle school students, whose objective was to introduce them to career opportunities, job interest, and financial help for pursuing a career objective in a technology field. The report describes program results from the summers of 1992, 1993 and 1996. It was administered through Eastern New Mexico University.

This paper describes a fiber-optic pH sensor based upon sol-gel encapsulation of a self-referencing dye, seminaphthorhodamine-1 carboxylate (SNARF-1C). The simple sol-gel fabrication procedure and low coating leachability are ideal for encapsulation and immobilization of dye molecules onto the end of an optical fiber. A miniature bench-top fluorimeter system was developed for use with the optical fiber to obtain pH measurements. Linear and reproducible responses were obtained in human blood in the pH range 6.8 to 8.0, which encompasses the clinically-relevant range. Therefore, this sensor can be considered for in vivo use.

The goals of this three-year study were: (1) design a neutron focusing system for use with the Texas Cold Neutron Source (TCNS) to produce an intense beam of cold neutrons appropriate for prompt gamma activation analysis (PGAA); (2) orchestrate the construction of the focusing system, integrate it into the TCNS neutron guide complex, and measure its performance; and (3) design, setup, and test a cold-neutron PGAA system which utilizes the guided focused cold neutron beam. During the first year of the DOE grant, a new procedure was developed and used to design a focusing converging guide consisting of truncated rectangular cone sections. Detailed calculations were performed using a 3-D Monte Carlo code which the authors wrote to trace neutrons through the curved guide of the TCNS into the proposed converging guide. Using realistic reflectivities for Ni-Ti supermirrors, the authors obtained gains of 3 to 5 for 4 different converging guide geometries. During the second year of the DOE grant, the subject of this final report, Ovonic Synthetic Materials Company was contracted to build a converging neutron guide focusing system to the specifications. Considerable time and effort were spent working with Ovonics on selecting the materials for the converging neutron guide …

This report verified the HVAC-DSC performed to the criteria stated in this functional test.

A conceptual design was performed of a light water moderated reactor with power output in the range of 1000 MWe, which allows passive decay heat removal (i.e., the heat path to the ultimate heat sink, ambient air, is provided by natural heat transfer mechanisms such as conduction, radiation and free convection). This eliminates the reliance on the availability of emergency pumped cooling. The design ensures that the fuel remains within safety limits even in the total absence of coolant in the primary system. The challenge met was the achievement of this passive cooling capability while simultaneously achieving a high, 1000 MWe power rating.

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Leak from Railcar/Tank Trailer. The calculations needed to quantify the risk associated with this accident scenario are included within.

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Subsurface Leak Remaining Subsurface. The calculations needed to quantify the risk associated with this accident scenario are included within.

In 1982, Construction Technology Laboratories (CTL), Portland Cement Association conducted additional sonic concrete nondestructive testing (NDT) in the Service Gallery on the south process (hot) cell walls and adjacent floor slab, including the locations where significant concrete degradation had been found by the 1981 sonic NDT. In the ceiling slabs, the anchor areas For the monorail hangers, and some visible cracks were sonic NDT inspected. CTL concluded that the hot cell walls have no significant reduction of structural capacity due to concrete degradation. Epoxy injection repairs were recommended by CTL for the damaged anchor areas and through depth cracks in the reinforced concrete ceiling slabs. When completed, the epoxy repairs should be inspected and confirmed with follow on sonic NDT. Lateral bracing for the Monorail system is also recommended to relieve the lateral loads on the hangers.

This Acceptance Test Report (ATR) documents the results of acceptance test procedure WHC-SD-WM-ATR-151. Included in this report is a summary of the tests, the results and issues, the signature and sign- off ATP pages, and a summarized table of the specification vs. ATP section that satisfied the specification.

In 1982, the damaged anchor areas (67 total) in the Operating Gallery and cold manipulator shop ceiling reinforced concrete slabs were epoxy injection repaired by Construction Technology Laboratories (CTL), Portland Cement Association. The through depth vertical cracks (10 total) in the ceiling slabs in the galleries and manipulator shops were sealed and structurally repaired using epoxy injection procedures. The details of the epoxy reRair are reported. Sonic nondestructive (NDT) testing before and after the epoxy injection repairs were made by CTL to confirm that the repairs are structurally effective. CTL recommended to expedite the installation of lateral bracing for the manipulator monorail in order to avoid re-darnage to the repaired anchor areas.

This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the AY-Farm Electrical Distribution; in the Equipment Removal System portion of Project W-320, functions as required by the design criteria.

This Acceptance Test Procedure (ATP) has been prepared to demonstrate that the C-Farm Electrical Distribution, in the Equipment Removal System portion of Project W-320, functions as required by the design criteria.

The authors describe how they have parallelized Python, an interpreted object oriented scripting language, and used it to build an extensible message-passing C/C++ applications for the CM-5, Cray T3D, and Sun multiprocessor servers running MPI. Using a parallelized Python interpreter, it is possible to interact with large-scale parallel applications, rapidly prototype new features, and perform application specific debugging. It is even possible to write message passing programs in Python itself. The authors describe some of the tools they have developed to extend Python and applications of this approach.

This annual report of the Hazards Control Department activities in 1995 is part of the department`s efforts to foster a working environment at Lawrence Livermore National Laboratory (LLNL) where every person desire to work safely.

This paper describes experiments to determine the sodium retention and drainage from the two key areas of an ID-69. This information is then used as the initiation point for guidelines of how to proceed with washing an ID-69 in the IEM Cell Sodium Removal System.

This project involves the development of an optimized, bench-scale processing circuit capable of efficiently removing trace elements from run-of-mine coals. The optimized circuit will be developed using characterization data obtained from detailed washability studies and release analyses tests conducted with several eastern U.S. coals. The optimized circuit will incorporate a variety of conventional and advanced coal cleaning processes. The coal products from the optimized circuit will be further treated with complexing agents specifically designed to extract organometallic trace elements that are difficult to remove by physical cleaning operations. Finally, innovative bioremediation schemes will be investigated as a means of controlling the release of trace elements from the process waste streams. Emphasis has been placed on the development of a processing circuit which (i) maximizes the rejection of trace elements, (ii) minimizes the production of coal fines which are costly to process and less marketable, and (iii) minimizes the downstream impacts of the process waste on the environment. During the past quarter, several key subtasks were completed. Most of the characterization tests for the Pittsburgh No. 8 coal have now been concluded. These include all activities associated with Subtasks 3.2 washability analysis, 3.3 flotation release analysis, and 3.4 SEM/image analysis. A …

Disconnecting the criticality alarm permanently in June 1996 signified that the hazards in the PUREX (plutonium-uranium extraction) plant had been so removed and reduced that criticality was no longer a credible event. Turning off the PUREX criticality alarm also marked a salient point in a historic deactivation project, 1 year before its anticipated conclusion. The PUREX/UO3 Deactivation Project began in October 1993 as a 5-year, $222.5- million project. As a result of innovations implemented during 1994 and 1995, the project schedule was shortened by over a year, with concomitant savings. In 1994, the innovations included arranging to send contaminated nitric acid from the PUREX Plant to British Nuclear Fuels, Limited (BNFL) for reuse and sending metal solutions containing plutonium and uranium from PUREX to the Hanford Site tank farms. These two steps saved the project $36.9- million. In 1995, reductions in overhead rate, work scope, and budget, along with curtailed capital equipment expenditures, reduced the cost another $25.6 million. These savings were achieved by using activity-based cost estimating and applying technical schedule enhancements. In 1996, a series of changes brought about under the general concept of ``reengineering`` reduced the cost approximately another $15 million, and moved the completion date to …

This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: HEPA Filter Failure - Exposure to High Temperature or Pressure. The calculations needed to quantify the risk associated with this accident scenario are included within.

The Single-Shell Tank (SST) system is a waste management unit within the Hanford Facility. The SST system is operating under interim status pending removal of the tank contents to the DST System and the closure of all SSTS. Storage is the principal function of the SST system and waste is no longer added to the tanks for storage. This document provides a single-shell tank system waste analysis plan.

This Tank Characterization Plan (ICP) identifies the information needed to address issues related to short-term and long-term safe storage and long-term management of single shell tank 241-T-1,10 (T- 110). It should be understood that needs and issues surrounding tank T-110 are evolving as new information becomes available. As a result, this TCP addresses only issues that have been identified to date. It is expected that changes may be necessary as additional issues or needs arise which impact the management of tank T-110. As necessary, this TCP will be revised to reflect changes. This plan reflects the best information available as of August 1996. Tank T-110 entered into service in the first quarter of 1945. The tank began receiving second- cycle decontamination waste in the first quarter of 1945 (Agnew et al. 1995). The tank began to cascade overflow to Tank 241-T-111 in October 1945. In the second quarter of 1952, the tank began receiving 224 waste in addition to the second-cycle waste. The tank contained second-cycle and 224 waste until the first quarter of 1976. During the third quarter of 1974, the tank received waste water. The tank was removed from service in 1976. A level adjustment was made in …

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-S-107. This report supports the requirements of Tri- Party Agreement Milestone M-44-09.

The purpose of this technical implementing procedure (TIP) is to describe the procedure that will be employed for user-calibration of a digital caliper used in the determination of specimen dimensions. A caliper is used for some of the activities of the Scientific Investigation Plan (SIP) Metal Barrier Selection and Testing (SIP-CM-01, WBS {number_sign} 1.2.2.5.1). In particular, it will be used for Activity E-20-50, Long-Term Corrosion Studies. This procedure describes the methodology for user calibration of a Fowler Ultra-Cal Mark III digital caliper. National Institutes of Standards and Technology (NIST) traceable gauge blocks are employed in the calibration procedure.

This waste analysis plan (WAP) has been prepared for the Low-Level Burial Grounds (LLBG) which are located in the 200 East and West Areas of the Hanford Facility, Richland, Washington. This WAP documents the methods used to characterize, and obtain and analyze representative samples of waste managed at this unit.