Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2 (open access)

Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2

The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification hairpin loop. However, without demineralization as a controlling agent, the gross non-volatile gamma activity levels of the reactor coolant increased and the specific activities of longlived fission products were at higher levels. Although the general levels of water- borne activities increased during the test period, the associated plant systems did not exceed their limits. (auth)
Date: July 21, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The neutrinos in muon decay (open access)

The neutrinos in muon decay

We review the available information on the identity of the neutrino states emitted in muon decay, and discuss the exotic decay {mu}{sup +} {yields} e{sup +} {bar {nu}}{sub e}{nu}{sub {mu}}. 22 refs.
Date: October 21, 1991
Creator: Herczeg, P.
Object Type: Article
System: The UNT Digital Library
High resolution x-ray crystal spectrographs (open access)

High resolution x-ray crystal spectrographs

Observation of x-ray line emissions are valuable for determining the thermodynamic state of the emitting plasma. For laser produced plasmas, diffraction crystals can be used to isolate x-ray monochromes to obtain high resolution spectral measurements. We will describe a versatile multi-crystal high resolution spectrograph used for photon energies from 0.5 to 6 keV. We will discuss a calculational package that tunes the response and sensitivity of the instrument and estimates the effect of source extent on spectral resolution. A scheme using fine slits to obtain spatial resolution with the basic instrument will also be described. An instrument is being built for Shiva diagnostics that incorporates a diffraction crystal and an x-ray streak camera. The design rationale for the crystal stage will be discussed.
Date: October 21, 1977
Creator: Koppel, L. N. & Eckels, J. D.
Object Type: Article
System: The UNT Digital Library
EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER (open access)

EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER

EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, group-dependent buckling, or region-dependent buckling may be specified for rectangular geometry. This program is intended to fill the need for a rapid two-dimensional calculation suitable for survey calculations. During the iterative part of the computations, all operations are carried out in the core memory. The magnetic tape memory is used only for input, output, and program storage. The running time for a 1000-point problem requiring 100 iterations would be about 3 min.(auth)
Date: February 21, 1962
Creator: Fowler, T.B. & Tobias, M.L.
Object Type: Report
System: The UNT Digital Library
CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961 (open access)

CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from granite, solvent extraction technology, mechanisms of separation processes, radiation effects on catalysts, ion exchange technology, chemical engineering research, chemical applications of nuclear explosions, reactor evaluation studies, and assistance programs. (J.R.D.)
Date: September 21, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Advanced development of a pressurized ash agglomerating fluidized-bed coal gasification system. Quarterly progress report, April 1-June 30, 1982 (open access)

Advanced development of a pressurized ash agglomerating fluidized-bed coal gasification system. Quarterly progress report, April 1-June 30, 1982

The overall objective of the Westinghouse coal gasification program is to demonstrate the viability of the Westinghouse pressurized, fluidized bed, gasification system for the production of medium-Btu fuel gas for syngas, electrical power generation, chemical feedstocks, or industrial fuels and to obtain performance and scaleup data for the process and hardware. Progress reports are presented for the following tasks: (1) operation and maintenance of the process development unit (PDU); (2) process analysis; (3) cold flow scaleup facility; (4) process and component engineering and design; and (5) laboratory support studies. Some of the highlights for this period are: TP-032-1, a single stage, oxygen-steam blown gasifier test was conducted in three operational phases from March 30, 1982 through May 2, 1982; TP-032-2 was conducted in two operational phases from May 20, 1982 through May 27, 1982; TP-032-1 and TP-032-2 successfully served as shakedown and demonstrations of the full cyclone cold wall; no visible deposits were found on the cold wall after processing highly fouling coals; samples of product gas produced during TP-032-1, were passed through four different scrubbing solutions and analyzed for 78 EPA primary organic pollutants, all of which were found to be below detection limits; TP-M004, a CO/sub 2/ tracer …
Date: October 21, 1982
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Evaluation of the radionuclide concentrations in soil and plants from the 1975 terrestrial survey of Bikini and Eneu Islands (open access)

Evaluation of the radionuclide concentrations in soil and plants from the 1975 terrestrial survey of Bikini and Eneu Islands

In June 1975 a radiological survey was conducted of the terrestrial environment of Bikini and Eneu islands (Bikini Atoll) to evaluate the potential radiation dose to the returning Bikini population. In this report, we present measurements of the radionuclide concentration in soil profiles and in dominant species of edible and nonedible, indicator plants. The use of these data to derive relationships to predict the plant uptake of radionuclides from soil is described. Approximately 620 soil and vegetation samples from Bikini and Eneu Islands were analyzed by Ge(Li) gamma spectrometry and by wet chemistry. The predominant radionuclides in these samples were /sup 60/Co, /sup 90/Sr, /sup 137/Cs, /sup 239,240/Pu, /sup 241/Pu, and /sup 241/Am.
Date: January 21, 1977
Creator: Colsher, C. S.; Robison, W. L. & Gudiksen, P. H.
Object Type: Report
System: The UNT Digital Library
Advanced development of a pressurized ash agglomerating fluidized-bed coal gasification system. Quarterly progress report, October 1-December 31, 1982 (open access)

Advanced development of a pressurized ash agglomerating fluidized-bed coal gasification system. Quarterly progress report, October 1-December 31, 1982

The overall objective of the Westinghouse coal gasification program is to demonstrate the viability of the Westinghouse pressurized, fluidized bed, gasification system for the production of medium-Btu fuel gas for syngas, electrical power generation, chemical feedstocks, or industrial fuels and to obtain performance and scaleup data for the process and hardware. Progress reports are presented for the following tasks: (1) operation and maintenance of the process development unit (PDU); (2) process analysis; (3) cold flow scaleup facility; (4) process component engineering and design; and (5) laboratory support studies involving gas solids flow modeling and coal/ash behavior. 9 figures, 19 tables.
Date: April 21, 1983
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Telephone costs at Princeton Plasma Physics Laboratory (open access)

Telephone costs at Princeton Plasma Physics Laboratory

The Princeton Plasma Physics Laboratory (PPPL) is a fusion energy research laboratory located on the Forrestal Campus of Princeton University in Plainsboro, New Jersey. Princeton University operates the laboratory under contact with the US Department of Energy (DOE). PPPL researches nuclear fusion and plasma physics and investigates the potential of a commercial fusion reactor. The objective of the audit was to determine whether PPPL was monitoring telephone use and costs in order to prevent personal toll costs from being charged to the DOE contract. Our audit disclosed that 5 out of the 10 PPPL cost centers we reviewed were not following established policies and procedures for monitoring telephone toll charges. This condition resulted because PPPL's management did not adequately review telephone use and costs. As a result, PPPL charged personal toll calls to DOE. Therefore, we recommend that the Manager, DOE Field Office, Chicago, (CH) direct PPPL to enforce its telephone policies and procedures to ensure that personal toll calls are not charged to DOE. The Acting Manager, CH, concurred with our recommendations and agreed to implement corrective actions.
Date: August 21, 1991
Creator: unknown
Object Type: Report
System: The UNT Digital Library
DEVELOPMENT OF RING-JOINT FLANGES FOR USE IN THE HRE-2 (open access)

DEVELOPMENT OF RING-JOINT FLANGES FOR USE IN THE HRE-2

Ring-joint flanges were studied in thermal-cycle tests as part of the development work associated with Homogeneous Reactor Experiment No. 2 (HRE-2). The purpose of this study was to provide criteria for design, installation, and operation of joints that would remain leaktight under reactor operating temperatures and pressures. Joints ranging from 1/2 in., l500 lb to 4 in., 2500 lb and with various initial bolt loadings were cycled between room temperature and 636 deg F. It was demonstrated that when joints were made up to HRE-2 standards and specifications, leak rates of less than 0.25 x 10/sup -3/ g of water per day per inch of gasket pitch diameter could be routinely- attained. Undamaged gaskets could be reinstalled or new gaskets used with equal probability of achieving acceptable leak rates. The system installed in HRE-2 was provided with a high-pressure buffer system to ensure that the small amount of leakage to the cell would be nonradioactive. (auth)
Date: December 21, 1961
Creator: Robinson, J. N.; Lundin, M. I. & Spiewak, I.
Object Type: Report
System: The UNT Digital Library
Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR] (open access)

Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR]

The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the effect of molten fuel on reactor structural or sacrificial material.
Date: March 21, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Environmental studies group. Annual report for 1978 (open access)

Environmental studies group. Annual report for 1978

Group projects included radioecological studies of aquatic and terrestrial systems, land management activities, foodstuff monitoring, dust transport studies including fugitive dust measurements and modeling, and several support programs involving evaluation of the plant's ambient air samplers and airborne tritium monitoring techniques. Some salient results from the several project reports include determination of an appropriate model for mechanically generated fugitive dust dispersion, a radionuclide inventory of Smart Ditch Pond (Pond D-1), a coefficient of community determination for two terrestrial sample plots on the plant site buffer zone, a natality and mortality rate determination for fawns in the plant deer herd (including one positive coyote-kill determination), inlet loss and filter paper collection efficiencies for the plant ambient air samplers, and differential tritium sampling measurements of the vapor in Building 771 stack effluent.
Date: August 21, 1980
Creator: Hunt, D. C. & Hurley, J. D.
Object Type: Report
System: The UNT Digital Library
Numerical analysis of laminar forced convection in a spherical annulus (open access)

Numerical analysis of laminar forced convection in a spherical annulus

Calculations of steady laminar incompressible fluid-flow and heat transfer in a spherical annulus are presented. Steady pressures, temperatures, velocities, and heat transfer coefficients are calculated for an insulated outer sphere and a 0/sup 0/C isothermal inner sphere with 50/sup 0/C heated water flowing in the annulus. The inner sphere radius is 13.97 cm, the outer sphere radius is 16.83 cm and the radius ratio is 1.2. The transient axisymmetric equations of heat, mass, and momentum conservation are solved numerically in spherical coordinates. The transient solution is carried out in time until steady state is achieved. A variable mesh is used to improve resolution near the inner sphere where temperature and velocity gradients are steep. It is believed that this is the first fully two-dimensional analysis of forced flow in a spherical annulus. Local and bulk Nusselt numbers are presented for Reynolds numbers from 4.4 to 440. Computed bulk Nusselt numbers ranged from 2 to 50 and are compared to experimental results from the literature. Inlet flow jetting off the inner sphere and flow separation are predicted by the analysis. The location of wall jet separation was found to be a function of Reynolds number, indicating the location of separation depends …
Date: July 21, 1980
Creator: Tuft, D.B.
Object Type: Article
System: The UNT Digital Library
Gene-enzyme telationships in somatic cells and their organismal derivatives in higher plants. Progress report (open access)

Gene-enzyme telationships in somatic cells and their organismal derivatives in higher plants. Progress report

Progress is reported in the following subject areas: (1) chemistry of the arogenate molecule; (2) plant enzymology at the organismal level; (3) isolation of regulatory mutants in tobacco; and (4) stability of the haploid state in Nicotiana sylvestris.
Date: April 21, 1980
Creator: Jensen, R. A.
Object Type: Report
System: The UNT Digital Library
Powerplant Productivity Improvement Study: project summary report (open access)

Powerplant Productivity Improvement Study: project summary report

Key findings from the Illinois Powerplant Productivity Improvement Study are: (1) the historic performance (equivalent availability) of large generating units in Illinois is below national average performance; (2) cost-effective opportunities to improve performance exist, and utilities pursue many of these; (3) there are no strong regulatory disincentives to the undertaking of productivity improvement projects, but no strong incentives either; (4) current utility practices, procedures, and management philosophy toward improved productivity are being strengthened; (5) areas in which immediate attention is warranted include application of reliability engineering tools to the analysis of powerplant availability and more vigorous pursuit of opportunities for performance improvements; (6) DOE systematic methodology for analysis of productivity improvement projects was demonstrated at three units and found to be useful; (7) the potential for improved productivity was estimated to be of the order of 2% in planned and forced outage rates; (8) if a 5% improvement were to be attained, cumulative (through 1990) constant-dollar benefits would be approximately $500 million; (9) formula regulatory incentive mechanisms are presently in a developmental or experimental phase, but adoption by the State of Illinois does not appear warranted at this time; and (10) the Illinois Commerce Commission can encourage improved productivity by …
Date: December 21, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Three-dimensional temperature history of a multipass filled weldment. Part 2. [HEATINGS] (open access)

Three-dimensional temperature history of a multipass filled weldment. Part 2. [HEATINGS]

Computer simulation of the three-dimensional temperature history in a multipass filled weldment was attempted by modifying a transient heat transfer code, HEATING5. The model includes temperature-dependent physical parameters, radiation and convection heat losses, turbulent and laminar convection in the molten pool, and variable arc velocity, intensity, and weld geometry. The model requires approximately 28 CPU min to simulate one second of welding. 15 figures, 8 tables.
Date: December 21, 1976
Creator: Pinkowish, J.A. & Whitman, P.K.
Object Type: Report
System: The UNT Digital Library
Annual environmental monitoring report: calendar year 1981 (open access)

Annual environmental monitoring report: calendar year 1981

The environment locally surrounding Mound was monitored primarily for tritium and plutonium-238. The results are reported for CY-1981. The environmental medium analyzed included air, water, vegetation, foodstuffs, and sediment. The average concentrations of plutonium-238 and tritium were within the applicable standards (adopted by the US DOE) for radioactive species.
Date: April 21, 1982
Creator: Farmer, B. M. & Carfagno, D. G.
Object Type: Report
System: The UNT Digital Library
Volume reduction system for solid and liquid TRU waste from the nuclear fuel cycle: October--December 1977 (open access)

Volume reduction system for solid and liquid TRU waste from the nuclear fuel cycle: October--December 1977

A bench-scale incinerator for the investigation of unusual particulate and gaseous radioactive material in the incinerator off-gas was assembled and equipment checkout was begun. Modifications to a glovebox to be used for the demonstration phase of incinerator-ash immobilization are approximately 80% completed with demonstration to begin next quarter. The curing time for ash-cement pressed pellets was optimized by periodic crush-strength testing of open-air and underwater cured samples. Leach tests were performed at 70 and 100/sup 0/C to simulate normal and extreme storage conditions. Long-term leach tests were initiated on plutonium-238 doped ash-cement pressed pellets in distilled water at ambient temperature. Pressed pellets of bone char, ash, and sludge-ash in several mixtures were fabricated and tested to establish pressing and curing parameters. Leach tests were also performed on bone char-cement pressed pellets. Curing studies have been conducted on the pressed pellet matrix to define differences between curing in the open atmosphere and under water. Leachability studies have been initiated on the pressed pellet ash/cement matrix in distilled water at ambient, 70 and 100/sup 0/C. Also, leachability studies on doped plutonium-238 pressed ash/cement pellets and pressed bone char/cement pellets in distilled water at ambient temperature have been conducted. Compressive strengths of bone …
Date: April 21, 1978
Creator: Luthy, D. F. & Bond, W.H.
Object Type: Report
System: The UNT Digital Library
Preliminary planning study for safety relief valve experiments in a Mark III BWR pressure suppression system (open access)

Preliminary planning study for safety relief valve experiments in a Mark III BWR pressure suppression system

In response to a request from the Water Reactor Safety Research Division of the US NRC, a preliminary study is provided which identifies key features and consideration involved in planning a comprehensive in-plant Safety Relief Valve experimental program for a Mark III containment design. The report provides identification of program objectives, measurement system requirements, and some details quantifying expected system response. In addition, a preliminary test matrix is outlined which involves a supporting philosophy intended to enhance the usefulness of the experimental results for all members of the program team: experimentalists, analysts, and plant operator.
Date: April 21, 1980
Creator: McCauley, E.W. & Holman, G.S.
Object Type: Report
System: The UNT Digital Library
PWR blowdown heat transfer separate-effects program data evaluation report: system response for thermal-hydraulic test facility test series 100 (open access)

PWR blowdown heat transfer separate-effects program data evaluation report: system response for thermal-hydraulic test facility test series 100

Selected reduced instrument responses and analyses of the indicated phenomena are presented for Thermal-Hydraulic Test Facility (THTF) test series 100, which is part of the PWR Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomena that govern the energy transfer and transport processes occurring during a postulated loss-of-coolant accident in a pressurized-water reactor system. Comparisons are made between the trends indicated by the reduced instrument responses and the thermal-hydraulic transient simulator RELAP4/MOD5 (update 2) to aid in understanding the phenomenological sequences. The results of verification studies of RELAP's performance in prediction of the THTF data are presented.
Date: October 21, 1977
Creator: Hedrick, R. A.; Craddick, W. G.; Turnage, K. G. & Hyman, C. R.
Object Type: Report
System: The UNT Digital Library
Interim report: studies of boron deposition near geothermal power plants (open access)

Interim report: studies of boron deposition near geothermal power plants

Measurements in the Geysers area from April until October 1979 when the onset of seasonal rains limited field work are presented. Field studies involved the following three basic types of measurements: cooling tower drift deposition, plant ecological studies, and animal population studies. Brief summaries of the data are presented to demonstrate the types of information obtained. (MHR)
Date: April 21, 1980
Creator: Koranda, J.J.
Object Type: Report
System: The UNT Digital Library
On-site waste storage assuring the success of on-site, low-level nuclear waste storage (open access)

On-site waste storage assuring the success of on-site, low-level nuclear waste storage

Waste management has reached paramount importance in recent years. The successful management of radioactive waste is a key ingredient in the successful operation of any nuclear facility. This paper discusses the options available for on-site storage of low-level radioactive waste and those options that have been selected by the Department of Energy facilities operated by Martin Marietta Energy Systems, Inc. in Oak Ridge, Tennessee. The focus of the paper is on quality assurance (QA) features of waste management activities such as accountability and retrievability of waste materials and waste packages, retrievability of data, waste containment, safety and environmental monitoring. Technical performance and careful documentation of that performance are goals which can be achieved only through the cooperation of numerous individuals from waste generating and waste managing organizations, engineering, QA, and environmental management.
Date: September 21, 1986
Creator: Preston, E.L.
Object Type: Article
System: The UNT Digital Library
Lawrence Livermore National Laboratory underground coal gasification data base. [US DOE-supported field tests; data] (open access)

Lawrence Livermore National Laboratory underground coal gasification data base. [US DOE-supported field tests; data]

The Department of Energy has sponsored a number of field projects to determine the feasibility of converting the nation's vast coal reserves into a clean efficient energy source via underground coal gasification (UCG). Due to these tests, a significant data base of process information has developed covering a range of coal seams (flat subbituminous, deep flat bituminous and steeply dipping subbituminous) and processing techniques. A summary of all DOE-sponsored tests to data is shown. The development of UCG on a commercial scale requires involvement from both the public and private sectors. However, without detailed process information, accurate assessments of the commercial viability of UCG cannot be determined. To help overcome this problem the DOE has directed the Lawrence Livermore National Laboratory (LLNL) to develop a UCG data base containing raw and reduced process data from all DOE-sponsored field tests. It is our intent to make the data base available upon request to interested parties, to help them assess the true potential of UCG.
Date: August 21, 1981
Creator: Cena, R. J. & Thorsness, C. B.
Object Type: Report
System: The UNT Digital Library
Modal photon densities (open access)

Modal photon densities

The short wavelength laser code XRASER uses line raidation fields whose dimensions are photons/mode. In this document, we discuss modal photon densities and provide formulas relating these units to units more familiar to the LLNL community.
Date: June 21, 1982
Creator: Hagelstein, P.L.
Object Type: Report
System: The UNT Digital Library