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Savannah River Plant 200 Area technical manual. Part SP. Processing of Np/sup 237/ and Pu/sup 238/
This manual covers the technology involved in the 200 Area process for the recovery of Np/sup 237/ from certain aqueous waste streams in the separations plants, for the recovery of NP/sup 237/ and Pu/sup 238/ from irradiated NpO/sub 2/-Al slugs and for the fabrication of NpO/sub 2/-Al slugs. The manual contains sections on the fundamental chemistry, the primary recovery of Np by ion exchange, the decontamination of Np by ion exchange, the processing of NpO/sub 2/-Al targets, the separation and purification of Np/sup 237/ and Pu/sup 238/, the finishing of Np, the preparation of NpO/sub 2/, the disposal of spent resin, and the safety aspects of the handling of hydrazine. The section on the fabrication of NpO/sub 2/-Al slugs will be added later. 76 refs., 22 figs.
Date:
January 3, 1963
Creator:
Hill, A.J. (comp.)
Object Type:
Report
System:
The UNT Digital Library
Congressional Oversight Manual
This report provides information about the Congressional Oversight Manual. Congressional Oversight of the executive is designed to fulfill a number of purposes like ensuring executive compliance with legislative intent etc.
Date:
January 3, 2007
Creator:
Kaiser, Frederick M.; Oleszek, Walter J.; Tatelman, Todd B.; Halstead, T. J. & Rosenberg, Morton
Object Type:
Report
System:
The UNT Digital Library
RadHeat V1 User's Manual
RadHeat is a one dimensional finite difference heat transfer code that can determine the transient temperature evolution of layered targets in pulsed penetrating radiation environments. It makes use of energy dependent opacity and stopping data to model the volumetric deposition of any number of photon or ion spectra each incident at arbitrary angles. Convective and radiative boundary conditions are handled as well as the ability to impose any initial temperature profile. The heat diffusion equation is formulated implicitly to eliminate timestep dependent stability issues. Simulations are, therefore, able to achieve high fidelity during times of thermal activity and greater speed elsewhere. The prototypical physical situation simulated by RadHeat is illustrated. RadHeat was originally written to study the temperature response of tungsten-armored target-facing walls to the pulsed photon and ion radiation emanating from fusion microexplosions in future IFE power plants. RadHeat's implementation is quite general, though, and the code can be applied to a very broad range of problems. Anything from the heating of the Earth's crust on a warm summer day to the temperature rise in a mirror after a laser pulse could potentially be modeled. This manual was written to help new users learn how to run the code …
Date:
January 3, 2005
Creator:
Abbott, R P
Object Type:
Text
System:
The UNT Digital Library
Operational and maintenance manual, 100 ton hydraulic trailer
The 100 ton hydraulic trailer is used to remove the mitigation pump from Tank 241SY101. This manual explains how to inspect, operate, and maintain the trailer in a state of readiness.
Date:
March 3, 1995
Creator:
Koons, B.M.
Object Type:
Report
System:
The UNT Digital Library
Colloid transport code-nuclear user`s manual
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.
Date:
April 3, 1992
Creator:
Jain, R.
Object Type:
Report
System:
The UNT Digital Library
NIF ICCS Test Controller for Automated & Manual Testing
The National Ignition Facility (NIF) Integrated Computer Control System (ICCS) is a large (1.5 MSLOC), hierarchical, distributed system that controls all aspects of the NIF laser [1]. The ICCS team delivers software updates to the NIF facility throughout the year to support shot operations and commissioning activities. In 2006, there were 48 releases of ICCS: 29 full releases, 19 patches. To ensure the quality of each delivery, thousands of manual and automated tests are performed using the ICCS Test Controller test infrastructure. The TestController system provides test inventory management, test planning, automated test execution and manual test logging, release testing summaries and test results search, all through a web browser interface. Automated tests include command line based frameworks server tests and Graphical User Interface (GUI) based Java tests. Manual tests are presented as a checklist-style web form to be completed by the tester. The results of all tests, automated and manual, are kept in a common repository that provides data to dynamic status reports. As part of the 3-stage ICCS release testing strategy, the TestController system helps plan, evaluate and track the readiness of each release to the NIF facility.
Date:
October 3, 2007
Creator:
Zielinski, J S
Object Type:
Article
System:
The UNT Digital Library
Service manual for installation,operation & maintenance of electric vegetable peeling machines
Blueprint depicting technical details of Battleship Texas.
Date:
July 3, 1941
Creator:
unknown
Object Type:
Technical Drawing
System:
The Portal to Texas History
Savannah River Site Ingestion Pathway Methodology Manual for Airborne Radioactive Releases
This manual documents a recommended methodology for determining the ingestion pathway consequences of hypothetical accidental airborne radiological releases from facilities at the Savannah River Site. Both particulate and tritiated radioactive contaminants are addressed. Other approaches should be applied for evaluation of routine releases.
Date:
January 3, 2001
Creator:
Vincent, A.W. III
Object Type:
Report
System:
The UNT Digital Library
Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual
This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.
Date:
February 3, 2000
Creator:
Irwin, J. J.
Object Type:
Report
System:
The UNT Digital Library
Study of job burnout in technical writers and technical illustrators/designers at LLNL
According to the American Institute of Stress, job stress is estimated to cost American industry more than $200 billion a year. These costs are, in part, related to the estimated 1 million employees that will be absent on an average workday because of stress; 75 percent of visits to primary care physicians are for stress-related problems. California workers' compensation claims for stress cost $1 billion for medical and legal fees alone (Murphy, 1997). But, there is another dimension to stress that needs to be addressed. Job stress can be a precursor to job burnout. Burnout is a loss of motivation, and antidotes for job stress will not necessarily alleviate or stop job burnout. Job burnout is experienced as exhaustion on physical, emotional, and cognitive levels. Burnout can include withdrawal and decreasing involvement on the job, seriously affecting job satisfaction, turnover, absenteeism, and productivity (Dwyer & Ganster, 1991; Erickson & Gunderson, 1972; Spector & Jex, 1991). The research project described in this paper examined whether job burnout exists in the technical writer and technical illustrator/designer occupations in the Technical Information Department at Lawrence Livermore National Laboratory. This study also determined at what age and after how many years of service these …
Date:
June 3, 1998
Creator:
Rice, J A
Object Type:
Report
System:
The UNT Digital Library
SRTC criticality safety technical review of SRT-CMA-930039
Review of SRT-CMA-930039, ``Nuclear Criticality Safety Evaluation (NCSE): DWPF Melter-Batch 1,`` December 1, 1993, has been performed by the Savannah River Technical Center (SRTC) Applied Physics Group. The NCSE is a criticality assessment of the Melt Cell in the DWPF. Additionally, this pertains only to Batch 1 operation, which differs from batches to follow. Plans for subsequent batch operations call for fissile material in the Salt Cell feed-stream, which necessitates a separate criticality evaluation in the future. The NCSE under review concludes that the process is safe from criticality events, even in the event that all lithium and boron neutron poisons are lost, provided uranium enrichments are less than 40%. Furthermore, if all the lithium and as much as 98% of the boron would be lost, uranium enrichments of 100% would be allowable. After a thorough review of the NCSE, this reviewer agrees with that conclusion. This technical review consisted of: an independent check of the methods and models employed, independent calculations application of ANSI/ANS 8.1, verification of WSRC Nuclear Criticality Safety Manual({sup 2}) procedures.
Date:
December 3, 1993
Creator:
Rathbun, R.
Object Type:
Report
System:
The UNT Digital Library
IRIS Final Technical Progress Report
OAK-B135 This NERI project, originally started as the Secure Transportable Autonomous Light Water Reactor (STAR-LW) and currently known as the International Reactor Innovative and Secure (IRIS) project, had the objective of investigating a novel type of water-cooled reactor to satisfy the Generation IV goals: fuel cycle sustainability, enhanced reliability and safety, and improved economics. The research objectives over the three-year (1999-2002) program were as follows: First year: Assess various design alternatives and establish main characteristics of a point design; Second year: Perform feasibility and engineering assessment of the selected design solutions; Third year: Complete reactor design and performance evaluation, including cost assessment These objectives were fully attained and actually they served to launch IRIS as a full fledged project for eventual commercial deployment. The program did not terminate in 2002 at the end of the NERI program, and has just entered in its fifth year. This has been made possible by the IRIS project participants which have grown from the original four member, two-countries team to the current twenty members, nine countries consortium. All the consortium members work under their own funding and it is estimated that the value of their in-kind contributions over the life of the project has …
Date:
November 3, 2003
Creator:
Carelli, M. D.
Object Type:
Report
System:
The UNT Digital Library
Technical bases for C-pile overbore test
The production gains and economic evaluation of overboring has been extensively treated. In this document, the justification for a trial attempt at overboring C-Reactor was given. The overboring test, covered by two production tests (one or overboring and one for fuel irradiation), requires the integration of efforts of Equipment Development, Process and Reactor Development, Process Technology, Manufacturing, and the Fuels Preparation Department. In view of this, it appears prudent to collect in one place the current design numbers with a word of explanation regarding their derivation. To this end, this document is dedicated.
Date:
November 3, 1960
Creator:
Curtiss, D. H.; Clinton, M. A. & Nechodom, W. S.
Object Type:
Report
System:
The UNT Digital Library
SITE LOGISTICS AND ADMINSITRATIVE SYSTEMS TECHNICAL REPORT
None
Date:
March 3, 1998
Creator:
United States. Department of Energy.
Object Type:
Report
System:
The UNT Digital Library
Aqueous Homogeneous Reactor Technical Panel Report
Considerable interest has been expressed for developing a stable U.S. production capacity for medical isotopes and particularly for molybdenum- 99 (99Mo). This is motivated by recent re-ductions in production and supply worldwide. Consistent with U.S. nonproliferation objectives, any new production capability should not use highly enriched uranium fuel or targets. Conse-quently, Aqueous Homogeneous Reactors (AHRs) are under consideration for potential 99Mo production using low-enriched uranium. Although the Nuclear Regulatory Commission (NRC) has guidance to facilitate the licensing process for non-power reactors, that guidance is focused on reactors with fixed, solid fuel and hence, not applicable to an AHR. A panel was convened to study the technical issues associated with normal operation and potential transients and accidents of an AHR that might be designed for isotope production. The panel has produced the requisite AHR licensing guidance for three chapters that exist now for non-power reactor licensing: Reac-tor Description, Reactor Coolant Systems, and Accident Analysis. The guidance is in two parts for each chapter: 1) standard format and content a licensee would use and 2) the standard review plan the NRC staff would use. This guidance takes into account the unique features of an AHR such as the fuel being in solution; …
Date:
December 3, 2010
Creator:
Diamond, David; Bajorek, Stephen; Bakel, Allen; Flanagan, George; Mubayi, Vinod; Skarda, Raymond et al.
Object Type:
Report
System:
The UNT Digital Library
Technical Analysis of Hydrogen Production: Evaluation of H2 Mini-Grids
We have assessed the transportation of hydrogen as a metal hydride slurry through pipelines over a short distance from a neighborhood hydrogen production facility to local points of use. The assessment was conducted in the context of a hydrogen "mini-grid" serving both vehicle fueling and stationary fuel cell power systems for local building heat and power. The concept was compared to a compressed gaseous hydrogen mini-grid option and to a stand-alone hydrogen fueling station. Based on our analysis results we have concluded that the metal hydride slurry concept has potential to provide significant reductions in overall energy use compared to liquid or chemical hydride delivery, but only modest reductions in overall energy use, hydrogen cost, and GHG emissions compared to a compressed gaseous hydrogen delivery. However, given the inherent (and perceived) safety and reasonable cost/efficiency of the metal hydride slurry systems, additional research and analysis is warranted. The concept could potentially overcome the public acceptance barrier associated with the perceptions about hydrogen delivery (including liquid hydrogen tanker trucks and high-pressure gaseous hydrogen pipelines or tube trailers) and facilitate the development of a near-term hydrogen infrastructure.
Date:
May 3, 2005
Creator:
Lasher, Stephen & Sinha, Jayanti
Object Type:
Report
System:
The UNT Digital Library
Technical Basis for Implementation of the PCM-1B for Personnel Release at Tank Farms
The purpose of this document is to define the technical basis and implementing guidelines for using automated personnel contamination monitors, such as the PCM-1B, at the River Protection Project (RPP) in lieu of performing a hand-held instrument followed by a PCM-1B survey for personnel release from contamination areas requiring a beta-gamma whole body survey. This document provides the basis for full implementation of the PCM-1B release survey, without the supplemental hand and foot survey, as currently implemented at RPP. This document applies only to RPP facilities. This document does not provide the technical basis for determining the equivalency of an automated system to hand-held instruments, or to the effective counting capability of automated systems as such technical determinations are contained in TBTN: GDGH-9604-RLS-0015.
Date:
December 3, 1999
Creator:
BROWN, R.L.
Object Type:
Report
System:
The UNT Digital Library
The CHPRC Groundwater and Technical Integration Support (Master Project) Quality Assurance Management Plan
The scope of the CH2M Hill Plateau Remediation Company, LLC (CHPRC) Groundwater and Technical Integration Support (Master Project) is for Pacific Northwest National Laboratory staff to provide technical and integration support to CHPRC. This work includes conducting investigations at the 300-FF-5 Operable Unit and other groundwater operable units, and providing strategic integration, technical integration and assessments, remediation decision support, and science and technology. The projects under this Master Project will be defined and included within the Master Project throughout the fiscal year, and will be incorporated into the Master Project Plan. This Quality Assurance Management Plan provides the quality assurance requirements and processes that will be followed by the CHPRC Groundwater and Technical Integration Support (Master Project) and all releases associated with the CHPRC Soil and Groundwater Remediation Project. The plan is designed to be used exclusively by project staff.
Date:
April 3, 2009
Creator:
Fix, N. J.
Object Type:
Report
System:
The UNT Digital Library
TASK TECHNICAL AND QUALITY ASSURANCE PLAN FOR GAMMA ASSAYS AT THE SRS SOLID WASTE MANAGEMENT FACILITIES
None
Date:
January 3, 2006
Creator:
CASELLA, VITO
Object Type:
Report
System:
The UNT Digital Library
Technical evaluation of the proposed design modifications and technical specification changes on grid voltage degradation (Part A) for the Peach Bottom Atomic Power Station, Units 2 and 3: selected issues program (Docket Nos. 50-277, 50-278)
This report documents the technical evaluation of the proposed design modification and Technical Specification changes for protection of Class 1E equipment from grid voltage degradation for the Peach Bottom Atomic Power Station, Units 2 and 3. The review criteria are based on several IEEE standards and The Code of Federal Regulations. The evaluation compares the submittals made by the plant with the NRC staff positions and the review criteria. The licensee meets the requirements of the NRC except for the submittal of proposed Technical Specification changes to substantiate the proposed circuit modifications and relay setpoints.
Date:
November 3, 1981
Creator:
White, R. L.
Object Type:
Report
System:
The UNT Digital Library
Develop apparatus and process for second-stage drying. Final technical report, September 26, 1994--September 27, 1996
The final technical report for this project contains detailed technical results for the various tasks performed in the projects. The project scope was to develop an apparatus and process for second-stage drying of softwoods, such as southern yellow pine, for construction lumber. The focus of the project was on increasing the efficiency of high-temperature drying. The project tasks were: (1) computer simulation refinement and extension of the theory to commercial-sized kilns, (2) detailed heat exchanger equipment design, (3) pilot-scale design and fabrication, (4) experimental evaluation of the pilot-scale system, and (5) preliminary design of a prototype system. The effort on this project has been continuous and productive in gaining a better understanding of the processes involved in the drying of softwoods. 19 refs., 41 figs., 13 tabs.
Date:
January 3, 1997
Creator:
Taylor, F.
Object Type:
Report
System:
The UNT Digital Library
A coal-fired combustion system for industrial process heating applications. Quarterly technical progress report, April 1992--June 1992
PETC has implemented a number of advanced combustion research projects that will lead to the establishment of a broad, commercially acceptable engineering data base for the advancement of coal as the fuel of choice for boilers, furnaces, and process heaters. Vortec Corporation`s Phase III development contract DE-AC22-91PC91161 for a ``Coal-Fired Combustion System for Industrial Process Heating Applications`` is project funded under the DOE/PETC advanced combustion program. This advanced combustion system research program is for the development of innovative coal-fired process heaters which can be used for high temperature melting, smelling and waste vitrification processes. The process heater concepts to be developed are based on advanced glass melting and ore smelting furnaces developed and patented by Vortec Corporation. The process heater systems to be developed have multiple use applications; however, the Phase III research effort is being focused on the development of a process heater system to be used for producing value added vitrified glass products from boiler/incinerator ashes and industrial wastes. The primary objective of the Phase III project is to develop and integrate all the system components, from fuel through total system controls, and then test the complete system in order to evaluate its potential marketability. During the current …
Date:
September 3, 1992
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
POC-scale testing of an advanced fine coal dewatering equipment/technique. Quarterly technical progress report 6, January--March 1996
Froth flotation technique is an effective and efficient process for recovering of ultra-fine clean coal. Economical dewatering of an ultra-fine clean coal product to a 20% level moisture will be an important step in successful implementation of the advanced cleaning processes. This project is a step in the Department of Energy`s program to show that ultra-clean coal could be effectively dewatered to 20% or lower moisture using either conventional or advanced dewatering techniques. The cost-sharing contract effort is for 36 months beginning September 30, 1994. This report discusses technical progress made during the quarter from January 1- March 31, 1996.
Date:
May 3, 1996
Creator:
Tao, D.; Groppo, J. G. & Parekh, B. K.
Object Type:
Report
System:
The UNT Digital Library
Technical Advice and Support for the Joint Integrated Non-Intrusive Inspection (JINII) Program Task 2.2 Transmission Digital Radiography (DR)
The Cargo Advanced Automated Radiography System (CAARS) program aims to utilize advanced radiographic systems to detect radiological and nuclear threats. Validation of initial design and testing concepts is a precondition for prototype system development and large-scale deployment. As expected, Depleted Uranium (DU) is a valid surrogate for Special Nuclear Materials (SNM) in CAARS Advanced Technology Demonstration (ATD) performance field-tests of transmission radiography systems. Dual-energy transmission measurements of DU are nearly identical to SNM, and are distinct from lower Z materials, provided the samples are matched to equal areal density. Results from an alternative method, using samples of equal thickness, showed sample discrimination by material density, rather than by atomic number (Z). The transmission measurements of DU and SNM were made with equipment that is nearly identical to current field systems. X-ray source beams at endpoint energies of 5.4 MeV and 9.6 MeV were used to measure transmission through the selected sample materials. The ratio of the x-ray linear attenuation coefficient times length ({micro}L) at 5.4 MeV, to {micro}L at 9.6 MeV is a metric for atomic number based discrimination of materials. The measured ratios were compared with computed values based on LLNL photon cross section data and LLNL developed models …
Date:
March 3, 2011
Creator:
Martz, H; Chinn, D & Pincus, C
Object Type:
Report
System:
The UNT Digital Library