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Advisory Council for Technical-Vocational Education in Texas Annual Report: 1983 (open access)

Advisory Council for Technical-Vocational Education in Texas Annual Report: 1983

Annual report of the Advisory Council for Technical-Vocational Education in Texas describing goals, activities, and accomplishments during fiscal year 1983
Date: December 31, 1983
Creator: Advisory Council for Technical-Vocational Education in Texas
Object Type: Report
System: The Portal to Texas History
Costs and impacts of transporting nuclear waste to candidate repository sites (open access)

Costs and impacts of transporting nuclear waste to candidate repository sites

In this paper, a status report on the current estimated costs and impacts of transporting high-level nuclear wastes to candidate disposal sites is given. Impacts in this analysis are measured in terms of risk to public health and safety. Since it is difficult to project the status of the nuclear industry to the time of repository operation - 20 to 50 years in the future - particular emphasis in the paper is placed on the evaluation of uncertainties. The first part of this paper briefly describes the characteristics of the waste that must be transported to a high-level waste disposal site. This discussion is followed by a section describing the characteristics of the waste transport system. Subsequent sections describe the costs and risk assessments of waste transport. Finally, in a concluding section, the effect of the uncertainties in the definition of the waste disposal system on cost and risk levels is evaluated. This last section also provides some perspectives on the magnitude of the cost and risk levels relative to other comparable costs and risks generally encountered. 13 references, 2 figures, 16 tables.
Date: December 31, 1983
Creator: McSweeney, T.I.; Peterson, R.W. & Gupta, R.
Object Type: Article
System: The UNT Digital Library
Disposal of high-level nuclear waste above the water table in arid regions (open access)

Disposal of high-level nuclear waste above the water table in arid regions

Locating a repository in the unsaturated zone of arid regions eliminates or simplifies many of the technological problems involved in designing a repository for operation below the water table and predicting its performance. It also offers possible accessibility and ease of monitoring throughout the operational period and possible retrieval of waste long after. The risks inherent in such a repository appear to be no greater than in one located in the saturated zone; in fact, many aspects of such a repository`s performance will be much easier to predict and the uncertainties will be reduced correspondingly. A major new concern would be whether future climatic changes could produce significant consequences due to possible rise of the water table or increased flux of water through the repository. If spent fuel were used as a waste form, a second new concern would be the rates of escape of gaseous {sup 129}I and {sup 14}C to the atmosphere.
Date: December 31, 1983
Creator: Roseboom, E.H. Jr.
Object Type: Report
System: The UNT Digital Library
Disproportionation and polymerization of plutonium(IV) in dilute aqueous solutions (open access)

Disproportionation and polymerization of plutonium(IV) in dilute aqueous solutions

The rates of polymerization and disproportionation of Pu(IV) have been studied using low concentrations: (1.7 - 10) x 10{sup -}M Pu, (0.8 - 12) x 10{sup -}M HCl and 0.0iM ionic strength. Osmium(II) complexes such as the tris-4,4`-2,2`-bipyridine complex were found to react rapidly with Pu(IV) but very slowly, if at all, with Pu(IV) polymer, Pu(III), or Pu(V). Thus, it is possible to determine unreacted Pu(IV) in the presence of rection products by using Os(II) complexes. Disproportionation reaction products, Pu(III) and Pu(V), were determined using their reactions with Ce(IV) sulfate. We find -d[Pu(IV)]/dt = k`[Pu(IV)]{sup 2} at constant pH. Log k` varies from about 4.25 at pH 3 to about 7.0 at pH 4.1 (units for k` are M{sup -1}min{sup -1}). The [H{sup +}] dependence varies from about -2 to -3 over the pH range studied. The measured rate is the sum of those for polymerization and disproportionation; the latter reaction amounts to about 75% of the total at pH 3 and 20% at pH 4. The second-order rate constants for disproportionation are very much larger than expected on the basis of extrapolation from 0.2 to 1.0M HC10{sub 4} solutions. The products of the reaction do not affect the rate, …
Date: December 31, 1983
Creator: Newton, T. W. & Rundberg, V. L.
Object Type: Article
System: The UNT Digital Library
Economics of mined geologic repositories (open access)

Economics of mined geologic repositories

During 1982, Congress considered legislation to provide for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel. The result of this legislative effort was the Nuclear Waste Policy Act of 1982 (NWPA), PL 97-425, signed into law January 7, 1983. An important part of the NWPA was the establishment of special funds in the US Treasury for Waste Disposal and Interim Storage to be financed by user fees to pay for all costs of the program. An initial fee of 1.0 mill per kilowatt-hour was specified. The Secretary was asked to annually review the amount of the fees established... to evaluate whether collection of the fee will provide sufficient revenues to offset the costs... In the event of a prospective fee cost mismatch, the Secretary was asked to propose an adjustment to the fee to insure full cost recovery. A series of studies were sponsored by DOE in 1982 to estimate program costs, to calculate the necessary fees to assure cost recovery, and to address uncertainties that could affect future program costs and consequent fee schedules. A brief summary of the 1982 cost estimates is presented. Sources of key cost uncertainties are discussed and …
Date: December 31, 1983
Creator: Hofmann, P.L. & Dippold, D.G.
Object Type: Article
System: The UNT Digital Library
Energy flow in an arctic aquatic ecosystem (open access)

Energy flow in an arctic aquatic ecosystem

This component of the terrestrial-aquatic interaction group seeks to use the natural stable carbon isotope ratios and radiocarbon abundances to trace the movement of photosynthate from the terrestrial environment to the stream system at MS-117. In addition to estimating the total flux, we will also attempt to describe the relative fractions derived from modern primary production and that derived from delayed inputs of eroded peat. We will also seek to determine the coupling efficiency of these energy sources to the invertebrate faunal populations in the tundra soils and streams.
Date: December 31, 1983
Creator: Schell, D. M.
Object Type: Report
System: The UNT Digital Library
Evaluation of DOE Radionuclide Solubility Data and Selected Retardation Parameters: Description of Calculational and Confirmatory Experimental Activities (open access)

Evaluation of DOE Radionuclide Solubility Data and Selected Retardation Parameters: Description of Calculational and Confirmatory Experimental Activities

An experimentally oriented program has been initiated to support the NRC analysis and licensing activities related to high-level nuclear waste repositories. The program will allow the NRC to independently confirm key geochemical values used in the site performance assessments submitted by the DOE candidate repository site projects. Key radionuclide retardation factor values, particularly radionuclide solubility and sorption values under site specific geochemical conditions, are being confirmed. The initial efforts are being directed toward basalt rock/groundwater systems relevant to the BWIP candidate site in the Pasco Basin. Future work will consider tuff (NNWSI candidate site in Yucca Mountain) and salt (unspecified ONWI bedded or domal salt sites) rock/groundwater systems. Initial experimental results with technetium have confirmed the BWIP values for basalt/groundwater systems under oxic redox conditions: high solubility and no sorption. Under reducing redox conditions, however, the experimental work did not confirm the proposed technetium values recommended by BWIP. In the presence of hydrazine to establish reducing conditions, an apparent solubility limit for technetium of about 5E-7 mol/L was encountered; BWIP recommended calculated values of 1E-12 or greater than or equal to 1E-14 mol/L. Experimental evidence concerning sorption of reduced technetium species is incomplete at this time. Equilibrium speciation and saturation …
Date: December 31, 1983
Creator: Kelmers, A. D.; Clark, R. J.; Cutshall, N. H.; Johnson, J. S. & Kessler, J. H.
Object Type: Article
System: The UNT Digital Library
[Experimental and theoretical plasma physics program]. [Final progress report, 1982--1983] (open access)

[Experimental and theoretical plasma physics program]. [Final progress report, 1982--1983]

In recent years, members of the Maryland Theory Group have made significant contributions to the national fusion theory programs, and, in many cases, these theoretical developments helped to interpret experimental results and to design new experimental programs. In the following, the authors summarize the technical progress in five major areas: (1) RF interaction with plasmas including wave propagation and RF heating, (2) spheromak formation, equilibrium, and stability; (3) stability of nonaxisymmetric systems (EBT, mirrors, etc.); (4) stability theory of toroidal plasmas (tokamak, RFP, etc); and (5) nonlinear theory.
Date: December 31, 1983
Creator: Griem, H.
Object Type: Report
System: The UNT Digital Library
First phase of small diameter heater experiments in tuff (open access)

First phase of small diameter heater experiments in tuff

As part of the Nevada Nuclear Waste Storage Investigations (NNWSI) project, we have undertaken small diameter heater experiments in the G-Tunnel Underground Facility on the Nevada Test Site (NTS). These experiments are to evaluate the thermal and hydrothermal behavior which might be encountered if heat producing nuclear waste were disposed of in welded and nonwelded tuffs. The two Phase I experiments discussed have focused on vertical borehole emplacements. In each experiment, temperatures were measured along the surface of the 10.2-cm-dia heater and the 12.7-cm-dia boreholes. For each experiment, measurements were compared with computer model representations. Maximum temperatures reached were: 196{sup 0}C for the welded tuff after 21 days of operations at 800W and 173{sup 0}C for the nonwelded tuff after 35 days of operations at 500W. Computed results indicate that the same heat transfer model (includes conduction and radiation only) can describe the behavior of both tuffs using empirical techniques to describe pore water vaporization. Hydrothermal measurements revealed heat-indiced water migration. Results indicated that small amounts of liquid water migrated into the welded tuff borehole early in the heating period. Once the rock-wall temperatures exceeded 94{sup 0}C, in both tuffs, there was mass transport of water vapor as evidence indicated …
Date: December 31, 1983
Creator: Zimmerman, R.M.
Object Type: Report
System: The UNT Digital Library
Geochemical similarities between volcanic units at Yucca Mountain and Pahute Mesa: evidence for a common magmatic origin for volcanic sequences that flank the Timber Mountain Caldera (open access)

Geochemical similarities between volcanic units at Yucca Mountain and Pahute Mesa: evidence for a common magmatic origin for volcanic sequences that flank the Timber Mountain Caldera

Chemical compositions have been determined for sanidine, plagioclase, biotite, and hornblende phenocrysts by electron microprobe for a comprehensive set of samples of Crater Flat Tuff and tuffs of Calico Hills. Most of these samples were obtained from drill holes at Yucca Mountain. Samples of tuffs and lavas of Area 20, obtained from locations at Pahute Mesa, have similarly been subjected to microprobe analysis. Complete modal petrography has been determined for all samples. Biotite and hornblende in the samples from both Yucca Mountain and Pahute Mesa have Fe-rich compositions that contract strikingly with Fe-poor compositions in the overlying Paintbrush Tuff and the underlying Lithic Ridge Tuff at Yucca Mountain. Each unit from Yucca Mountain has distinctive compositions for both sanidine and plagioclase that very closely match compositions for a corresponding unit identified within the lower, middle and upper portions of the Area 20 tuffs and lavas from Pahute Mesa. Each of these paired units probably originated from a common parental magma and was eruptd contemporaneously or nearly so. Each pair of units with matching phenocryst chemistries has a similar, but not identical set of petrographic characteristics. The petrographic differences, as well as small differences in phenocryst chemistry, result from a sonal …
Date: December 31, 1983
Creator: Warren, R.G.
Object Type: Report
System: The UNT Digital Library
Geologic and geophysical investigations of Climax stock intrusive, Nevada (open access)

Geologic and geophysical investigations of Climax stock intrusive, Nevada

This document contains three parts of a survey of Climax stock intrusive, Nevada by the US Geological Survey. The first contains the results of a conventional survey of the site and an investigation of rock composition. The second contains the results of a gravity survey and the third contains the results of a magnetic aerial survey. Each of the three documents contains a separate abstract.
Date: December 31, 1983
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Geologic and hydrologic characterization and evaluation of the Basin and Range Province relative to the disposal of high-level radioactive waste. Part III. Geologic and hydrolic evaluation (open access)

Geologic and hydrologic characterization and evaluation of the Basin and Range Province relative to the disposal of high-level radioactive waste. Part III. Geologic and hydrolic evaluation

The geologic and hydrologic factors considered in the Province evaluation include distribution of potential host rocks, tectonic conditions and data on ground-water hydrology. Potential host media considered include argillaceous rocks, tuff, basaltic rocks, granitic rocks, evaporites, and the unsaturated zone. The tectonic factors considered are Quaternary faults, late Cenozoic volcanics, seismic activity, heat flow, and late Cenozoic rates of vertical uplift. Hydrologic conditions considered include length of flow path from potential host rocks to discharge areas, interbasin and geothermal flow systems and thick unsaturated sections as potential host media. The Basin and Range Province was divided into 12 subprovinces; each subprovince is evaluated separately and prospective areas for further study are identified. About one-half of the Province appears to have combinations of potential host rocks, tectonic conditions, and ground-water hydrology that merit consideration for further study. The prospective areas for further study in each subprovince are summarized in a brief list of the potentially favorable factors and the issues of concern. Data compiled for the entire Province do not permit a complete evaluation of the favorability for high-level waste isolation. The evaluations here are intended to identify broad regions that contain potential geohydrologic environments containing multiple natural barriers to radionuclide …
Date: December 31, 1983
Creator: Bedinger, M.S.; Sargent, K.A. & Brady, B.T.
Object Type: Report
System: The UNT Digital Library
Groundwater monitoring in the Savannah River Plant Low Level Waste Burial Ground (open access)

Groundwater monitoring in the Savannah River Plant Low Level Waste Burial Ground

This document describes chemical mechanisms that may affect trace-level radionuclide migration through acidic sandy clay soils in a humid environment, and summarizes the extensive chemical and radiochemical analyses of the groundwater directly below the SRP Low-Level Waste (LLW) Burial Ground (643-G). Anomalies were identified in the chemistry of individual wells which appear to be related to small amounts of fission product activity that have reached the water table. The chemical properties which were statistically related to trace level transport of Cs-137 and Sr-90 were iron, potassium, sodium and calcium. Concentrations on the order of 100 ppM appear sufficient to affect nuclide migration. Several complexation mechanisms for plutonium migration were investigated.
Date: December 31, 1983
Creator: Carlton, W. H.
Object Type: Report
System: The UNT Digital Library
[Hadroproduction of charmed and bottom mesons (Fermilab experiment E-653): Progress report, April 1, 1982--March 31, 1983] (open access)

[Hadroproduction of charmed and bottom mesons (Fermilab experiment E-653): Progress report, April 1, 1982--March 31, 1983]

This progress report describes several projects that U of Oklahoma has participated in. The first is a muon background calculation from decay of charged pions and kaons, using ISR data at center of mass energies of 31 and 53 GeV. These calculations were compared with a number of different events. A copy of an agreement between Fermi National Accelerator Laboratory and participants in experiment E-653 is enclosed. This experiment tags charm and beauty particles by observing their decay lengths. The agreement sets out the items which need to be done in order to properly execute this experiment. A program to construct and test prototype silicon stripe detectors is also described. Preliminary detectors are in hand for testing, some are installed for actual beams for testing, and on the basis of these results the group expects to specify the design for a new system. The goals at present are to check charge collection, to check track point resolution, and to check vertex reconstruction resolution. A copy of a letter of intent to submit a proposal to LEP is included. The group proposes to submit a proposal to build an experiment with approximately 1% momentum resolution at 50 GeV/c for identifying photons, …
Date: December 31, 1983
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Map showing surficial geology of the Lathrop Wells Quadrangle, Nye County, Nevada (open access)

Map showing surficial geology of the Lathrop Wells Quadrangle, Nye County, Nevada

This map shows the geology of the Lathrop Wells quadrangle located just south of the Nevada Test Site. 6 refs.
Date: December 31, 1983
Creator: Swadley, W. C.
Object Type: Report
System: The UNT Digital Library
Numerical simulation of flow and transport in partially saturated, fractured tuff (open access)

Numerical simulation of flow and transport in partially saturated, fractured tuff

The unsaturated, fractured tuff of Yucca Mountain in the Nevada Test Site is one of the target sites for geologic storage of high-level radioactive waste. A modeling study of flow and transport in this geologically complex site is presented. Numerical models of mass and heat flow in conjunction with analytical solutions are being used for sensitivity and pathway analysis studies and to aid in design and interpretation of laboratory and field flow and transport tests in tuff. 11 references, 9 figures, 1 table.
Date: December 31, 1983
Creator: Travis, B. J.; Hodson, S. W.; Cook, T. L.; Nuttall, H. E. & Rundberg, R.
Object Type: Article
System: The UNT Digital Library
Post emplacement environment of waste packages (open access)

Post emplacement environment of waste packages

Experiments have been conducted as part of the Nevada Nuclear Waste Storage Investigations Project to determine the changes in water chemistry due to reaction of the Topopah Spring tuff with natural groundwater at temperatures up to 150{sup 0}C. The reaction extent has been investigated as a function of rock-to-water ratio, temperature, reaction time, physical state of the samples, and geographic location of the samples within the tuff unit. Results of these experiments will be used to provide information on the water chemistry to be expected if a high-level waste repository were to be constructed in the Topopah Spring tuff. 6 references, 5 figures, 1 table.
Date: December 31, 1983
Creator: Knauss, K.G.; Oversby, V.M. & Wolery, T.J.
Object Type: Report
System: The UNT Digital Library
Preliminary design of the Carrisa Plains solar central receiver power plant. Volume I. Executive summary (open access)

Preliminary design of the Carrisa Plains solar central receiver power plant. Volume I. Executive summary

The design of the 30 MWe central receiver solar power plant to be located at Carrisa Plains, San Luis Obispo County, California, is summarized. The plant uses a vertical flat-panel (billboard) solar receiver located at the top of a tower to collect solar energy redirected by approximately 1900 heliostats located to the north of the tower. The solar energy is used to heat liquid sodium pumped from ground level from 610 to 1050/sup 0/F. The power conversion system is a non-reheat system, cost-effective at this size level, and designed for high-efficiency performance in an application requiring daily startup. Successful completion of this project will lead to power generation starting in 1986. This report also discusses plant performance, operations and maintenance, development, and facility cost estimate and economic analysis.
Date: December 31, 1983
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Preliminary design of the Carrisa Plains solar central receiver power plant. Volume III, Book 1. Design description (open access)

Preliminary design of the Carrisa Plains solar central receiver power plant. Volume III, Book 1. Design description

The design of the 30 MWe central receiver solar power plant to be located at Carrisa Plains, San Luis Obispo County, California, is summarized. The plant uses a vertical flat-panel (billboard solar receiver located at the top of a tower to collect solar energy redirected by approximately 1900 heliostats located to the north of the tower. The solar energy is used to heat liquid sodium pumped from ground level from 610 to 1050/sup 0/F. The power conversion system is a non-reheat system, cost-effective at this size level, and designed for high-efficiency performance in an application requiring daily startup. Successful completion of this project will lead to power generation starting in 1986. This report discusses in detail the design of the collector system, heat transport system, thermal storage subsystem, heat transport loop, steam generation subsystem, electrical, instrumentation, and control systems, power conversion system, master control system, and balance of plant. The performance, facility cost estimate and economic analysis, and development plan are also discussed.
Date: December 31, 1983
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Review of a field study of radionuclide migration from an underground nuclear explosion at the Nevada Test Site (open access)

Review of a field study of radionuclide migration from an underground nuclear explosion at the Nevada Test Site

Results from a long-term (9 year) field study of the distribution of radionuclides around an underground nuclear explosion cavity at the Nevada Test Site are reviewed. The goals of this Radionuclide Migration project are to examine the rates of migration underground in various media and to determine the potential for movement, both on and off the Nevada Test Site, of radioactivity from such explosions, with particular interest in possible contamination of water supplies. Initial studies were undertaken near the site of the low-yield test Cambric, which was detonated 73 m beneath the water table in tuffaceous alluvium. Solid samples were obtained from just below ground surface to 50 m below the detonation point, and water was sampled from five different regions in the vicinity of the explosion. Ten years after the test, most of the radioactivity was found to be retained in the fused debris in the cavity region and no activity above background was found 50 m below. Only tritium and {sup 90}Sr were presented in water in the cavity at levels greater than recommended concentration guides for water in uncontrolled areas. A satellite well is being used to remove water 91 m from the detonation point. During seven …
Date: December 31, 1983
Creator: Hoffman, D. C.; Daniels, W. R.; Wolfsberg, K.; Thompson, J. L.; Rundberg, R. S.; Fraser, S. L. et al.
Object Type: Article
System: The UNT Digital Library
Studies of altered vitrophyre for the prediction of nuclear waste repository - induced thermal alteration at Yucca Mountain, Nevada (open access)

Studies of altered vitrophyre for the prediction of nuclear waste repository - induced thermal alteration at Yucca Mountain, Nevada

Nuclear waste emplacement in devitrified volcanic tuff at Yucca Mountain will raise the temperature of surrounding rock for a geologically significant period of time. This study evaluates the susceptibility of an underlying 50-ft-thick vitrophyre to thermal alteration by examining alteration that occured in the rock as it cooled after deposition. A 10{sup 0}C temperature rise should have no mineralogical effects on the vitrophyre, but an increase of 60{sup 0} or more is likely to result in alteration. Expected mineralogic changes in the vitrophyre caused by this amount of thermal loading include crystallization of zeolites and smectite. Alteration will be concentrated of zeolites and smectite. Alteration will be concentrated in a thin interval near the top of the vitrophyre and along fractures. Adsorbed water and water in preexisting hydrous minerals and in glass may contribute to hydrothermal alteration of underlying vitrophyre. Bulk porosity change would be slight and local porosity increase would probably be restricted to the upper part of the vitrophyre. Although some fracture filling could occur, such a minor sealing effect would be balanced by development of secondary porosity. Zeolites and smectite, newly-crystallized along fluid flow paths below the waste repository, could provide an enhanced sorptive barrier to radionuclide …
Date: December 31, 1983
Creator: Levy, S.S.
Object Type: Article
System: The UNT Digital Library
Surveys for desert tortoise on the proposed site of a high-level nuclear waste repository at the Nevada Test Site (open access)

Surveys for desert tortoise on the proposed site of a high-level nuclear waste repository at the Nevada Test Site

The National Waste Terminal Storage Program is a national search for suitable sites to isolate commercial spent nuclear fuel or high-level radioactive waste. The Nevada Nuclear Waste Storage Investigation (NNWSI) managed by the U.S. Department of Energy (DOE), Nevada Operations Office, was initiated to study the suitability of a portion of Yucca Mountain on the DOE`s Nevada Test Site (NTS) as a location for such a repository. EG and G was contracted to provide information concerning the ecosystems encountered on the site. A comprehensive literature survey was conducted to evaluate the status and completeness of the existing biological information for the previously undisturbed area. Site specific studies were begun in 1981 when preliminary field surveys confirmed the presence of the desert tortoise (Gopherus agassizi) within the project area FY82 studies were designed to determine the overall distribution and abundance of the tortoise within the area likely to be impacted by NNWSI activities. The Yucca Mountain area of the Nevada Test Site is situated close to the northern range limit of the desert tortoise. Prior to the 1982 surveys, the desert tortoise was reported from only nine locations on NTS. A known population had been under study in Rock Valley about …
Date: December 31, 1983
Creator: Collins, Elizabeth; Sauls, Mary L. & O`Farrell, Thomas P.
Object Type: Article
System: The UNT Digital Library
Texas Preventable Disease News, Volume 43, Number 52, December 31, 1983 (open access)

Texas Preventable Disease News, Volume 43, Number 52, December 31, 1983

Newsletter of the Texas Bureau of Disease Control and Epidemiology discussing the news, activities, and events of the organization and other information related to health in Texas. This issue includes the subject index for 1983.
Date: December 31, 1983
Creator: Texas. Bureau of Disease Control and Epidemiology.
Object Type: Journal/Magazine/Newsletter
System: The Portal to Texas History
Designer's Guidebook for First Wall/Blanket/Shield Assembly, Maintenance, and Repair (open access)

Designer's Guidebook for First Wall/Blanket/Shield Assembly, Maintenance, and Repair

This is the initial issue of the guidebook. Since a guidebook of this type must incorporate information concerning a wide range of subjects, much additional data will eventually be included. The guidebook will document, in summary and easily referenceable form, data, designs, design concepts, design guidelines and background information useful to the FWBS and to the Maintenance System designer. In providing guidelines for the AMR of the FWBS, the guidebook must, of necessity, include guidelines for all aspects of maintenance associated with the FWBS. These include most maintenance operations within the reactor room necessary to gain access, identify faults, and handle equipment related to FWBS maintenance. In addition, the guidelines include those required to define facility requirements for handling and repair of FWBS and related reactor components external to the reactor room. Particular emphasis is given to remote maintenance design and operations.
Date: December 30, 1983
Creator: unknown
Object Type: Report
System: The UNT Digital Library