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Summary data for U. S. commercial nuclear power plants in the United States (open access)

Summary data for U. S. commercial nuclear power plants in the United States

A compilation of data is presented for all United States commercial nuclear power plants for which a construction permit application was made through the Nuclear Regulatory Commission. The data are compiled in four separate tables with cross-referencing indexes: Table 1--General Data; Table 2--Reactor Data; Table 3--Site Data, and Table 4--Circulating-Water System Data. The power plants are listed in numerical order by docket number in all four tables.
Date: March 20, 1978
Creator: Heddleson, F.A.
Object Type: Report
System: The UNT Digital Library
Recent results from studies of non-gaseous fission products with TRISTAN II (open access)

Recent results from studies of non-gaseous fission products with TRISTAN II

A new in-beam target ion-source combination has been installed at the TRISTAN isotope separator facility. Mass separated beams of nongaseous fission products are now available for study. Studies of levels in even-even Cd and Sn nuclei populated through the decay of Ag and In fission products are described, and an evaluation of possibilities for future research is made.
Date: March 1, 1978
Creator: Hill, J. C.
Object Type: Report
System: The UNT Digital Library
Studies of evaporative and conventional cooling of an energy conserving California house (open access)

Studies of evaporative and conventional cooling of an energy conserving California house

For cooling a Sacramento, California home, (1) higher thermostat settings, (2) insulation (3) ''solar control'' window shades, and (4) the use of an evaporative cooler in the place of a vapor compression cycle air conditioner are studied. A computer program TWOZONE is used to evaluate the effect on energy consumption and peak power. It is calculated that the peak cooling load can be reduced by a factor of 5 or more and the total energy by a factor of 20 or more.
Date: March 1, 1978
Creator: Gates, S.D.; Baughn, J. & Rosenfeld, A.H.
Object Type: Article
System: The UNT Digital Library
Blast tests of expedient shelters in the DICE THROW event (open access)

Blast tests of expedient shelters in the DICE THROW event

To determine the worst blast environments that eight types of expedient shelters can withstand, we subjected a total of 18 shelters to the 1-kiloton blast effects of Defense Nuclear Agency's DICE THROW main event. These expedient shelters included two Russian and two Chinese types. The best shelter tested was a Small-Pole Shelter that had a box-like room of Russian design with ORNL-designed expedient blast entries and blast doors added. It was undamaged at the 53-psi peak overpressure range; the pressure rise inside was only 1.5 psi. An unmodified Russian Pole-Covered Trench Shelter was badly damaged at 6.8 psi. A Chinese ''Man'' Shelter, which skillfully uses very small poles to attain protective earth arching, survived 20 psi, undamaged. Two types of expedient shelters built of materials found in and around most American homes gave good protection at overpressures up to about 6 psi. Rug-Covered Trench Shelters were proved unsatisfactory. Water storage pits lined with ordinary plastic trash bags were proven practical at up to 53 psi, as were triangular expedient blast doors made of poles.
Date: March 1, 1978
Creator: Kearny, C. H. & Chester, C. V.
Object Type: Report
System: The UNT Digital Library
Calculated hadronic transmission through iron absorbers (open access)

Calculated hadronic transmission through iron absorbers

The transmission of hadrons through iron absorbers is investigated for a variety of experimental configurations, and incident particle types (protons, and charged pions) and energies (0.8 GeV/c to 100 GeV). The results obtained are consistent with available experimental data.
Date: March 1, 1978
Creator: Gabriel, T. A. & Bishop, B. L.
Object Type: Report
System: The UNT Digital Library
Some atmospheric tracer experiments in complex terrain at LASL: experimental design and data. [Fluorescent particle tracer study] (open access)

Some atmospheric tracer experiments in complex terrain at LASL: experimental design and data. [Fluorescent particle tracer study]

Two series of atmospheric tracer experiments were conducted in complex terrain situations in and around the Los Alamos Scientific Laboratory. Fluorescent particle tracers were used to investigate nighttime drainage flow in Los Alamos Canyon and daytime flow across the local canyon-mesa complex. This report describes the details of these experiments and presents a summary of the data collected. A subsequent report will discuss the analysis of these data.
Date: March 1, 1978
Creator: Archuleta, J.; Barr, S.; Clements, W.E.; Gedayloo, T. & Wilson, S.K.
Object Type: Report
System: The UNT Digital Library
Radiation emergency response in Illinois, Alabama, and Texas (open access)

Radiation emergency response in Illinois, Alabama, and Texas

The objective of this study was to examine state radiation emergency response and to locate any areas of emergency planning in need of improvement. This report briefly presents a summary of laws and defining documents governing radiation emergency response, describes the existing and projected need for such response, and presents the authors' analyses of the evolution of state response plans and their application to radiation incidents. Three states' programs are discussed in detail: Illinois, Alabama, and Texas. These states were selected because they have quite different emergency-response programs. Therefore, these state programs provide a wide variety of approaches to state radiation emergency response.
Date: March 1, 1978
Creator: Larsen, D. K. & Chester, R. O.
Object Type: Report
System: The UNT Digital Library
Investigation of methylpentene polymer (TPX) molding resin. Final report (open access)

Investigation of methylpentene polymer (TPX) molding resin. Final report

A polymethylpentene polymer (TPX) produced by Mitsui Petrochemical Industries, Ltd., Japan, was evaluated and compared to a TPX previously obtained from Imperial Chemical Industries, Ltd., England, who no longer produce TPX and have sold their manufacturing process for this polymer to Mitsui. The rheological, chemical, and physical properties of the materials were compared and the two materials were found to be essentially identical.
Date: March 1, 1978
Creator: Walter, C.L.
Object Type: Report
System: The UNT Digital Library
Hydraulic pressure pulses with elastic and plastic structural flexibility: test and analysis (LWBR Development Program) (open access)

Hydraulic pressure pulses with elastic and plastic structural flexibility: test and analysis (LWBR Development Program)

Pressure pulse tests were conducted with a flexible test section in a test vessel filled with room temperature water. The pressure pulses were generated with a drop hammer and piston pulse generator and were of a sufficient magnitude to cause plastic deformation of the test section. Because of the strong pressure relief effect of the deforming test section, pressure pulse magnitudes were below 265 psig in magnitude and had durations of 50 to 55 msecs. Calculations performed with the FLASH-35 bi-linear hysteresis model of structural deformation show good agreement with experiment. In particular, FLASH 35 adequately predicts the decrease in peak pressure and the increase in pulse duration due to elastic and plastic deformation of the test section. Predictions of flexible member motion are good, but are less satisfactory than the pressure pulse results due to uncertainties in the values of yield point and beyond yield stiffness used to model the various flexible members. Coupled with this is a strong sensitivity of the FLASH 35 predictions to the values of yield point and beyond yield stiffness chosen for the various flexible members. The test data versus calculation comparisons presented here provide preliminary qualification for FLASH 35 calculations of transient hydraulic …
Date: March 1978
Creator: Schwirian, R. E.
Object Type: Report
System: The UNT Digital Library
Identification of potential participant scientists and development of procedures for a national inventory of selected biological monitoring programs: a mail questionnaire survey (open access)

Identification of potential participant scientists and development of procedures for a national inventory of selected biological monitoring programs: a mail questionnaire survey

Procedural details of how the National Biological Monitoring Inventory was conducted are described. Results of a nationwide telephone campaign to identify principal investigators and also of a nationwide questionnaire mailing to the investigators identified are presented. On the basis of percentage of questionnaire returns (nearly 50 percent), the Inventory was judged to be successful. The communication procedures, guidelines, and formats developed may be useful to others engaged in this type of research.
Date: March 1, 1978
Creator: Kemp, H.T.; Goff, F.G. & Ross, J.W.
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
Guiding center simulations of strong ion beams with applications to the Counterstreaming Ion Torus (open access)

Guiding center simulations of strong ion beams with applications to the Counterstreaming Ion Torus

In the proposed Counterstreaming Ion Torus (CIT) steady state rather than pulsed operation may be possible if all of the plasma power density is provided by neutral beam injection. After the neutral beams have penetrated the magnetic field, strong ion beam currents are produced. A major concern with the relatively strong counterstreaming ion currents is the effect of the beam self-magnetic fields on the macroscopic equilibrium of the system. Pinching and self focusing of the individual beams may occur, or the repulsive interaction of the two oppositely directed beam currents may destroy the equilibrium entirely. We investigate this macroscopic behavior of the ion beams with a guiding center plasma particle simulation model and we describe a model we have developed to simulate steady state behavior in an ideal CIT configuration.
Date: March 1, 1978
Creator: Tull, C.
Object Type: Report
System: The UNT Digital Library
Kilowatt Isotope Power System: component test procedure for the ground demonstration system jet condenser focusing. 77-KIPS-59. Revision A (open access)

Kilowatt Isotope Power System: component test procedure for the ground demonstration system jet condenser focusing. 77-KIPS-59. Revision A

This test procedure (No. 404A) provides a detailed description of the verification methods which shall be used in the development program to be conducted on the Kilowatt Isotope Power System (KIPS) Jet Condenser to fulfill the requirements of the Ground Demonstration Test Plan, Section 6.4. This is a revision of Test Procedure No. 404.
Date: March 14, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Supplement to CAMAC standards and reports. Computer automated measurement and control (open access)

Supplement to CAMAC standards and reports. Computer automated measurement and control

Several Department of Energy and IEEE Standards and reports are concerned with the CAMAC modular instrumentation and digital interface system. Since, these documents are under continual review, clarifications, corrections and modifications are made from time to time. This supplement compiles all such material in a single document that is to be revised and reissued as necessary.
Date: March 1, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Development of a metallographic method for tungsten--rhenium. Final report (open access)

Development of a metallographic method for tungsten--rhenium. Final report

A metallographic method was developed for chemical vapor deposited tungsten-rhenium alloys consisting of a two-phase structure of ..beta.. solid solution and a finely dispersed A-15 or federite phase. This method provides fast and reliable information on the structure and composition of the CVD deposit.
Date: March 1, 1978
Creator: Rahe, A.H.
Object Type: Report
System: The UNT Digital Library
PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 103 (open access)

PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 103

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 103, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system.
Date: March 7, 1978
Creator: Clemons, V. D.; White, M. D.; Moore, P. A. & Hedrick, R. A.
Object Type: Report
System: The UNT Digital Library
Simulation modeling of an automated material storage/retrieval system. [GPSS] (open access)

Simulation modeling of an automated material storage/retrieval system. [GPSS]

A computer simulation model is presented for an automated material storage-and-retrieval system that utilizes bin loading. The model is written in General Purpose Simulation System (GPSS) language, and it functionally simulates incoming job-arrival rates, operator task times, and the travel times of the storage/retrieval vehicle. The model is utilized to evaluate the impact of employing different types of storage policies, the duration of wait times encountered in a priority batch queue, and the expected throughput capacity of the system under either maximum-input or peak-period conditions.
Date: March 1, 1978
Creator: Gallegos, J.
Object Type: Report
System: The UNT Digital Library
Remeasurement of permanent vegetation plots in the Great Smoky Mountains National Park, Tennessee, USA, and the implications of climatic changes on vegetation. Environmental Sciences Division publication No. 1111 (open access)

Remeasurement of permanent vegetation plots in the Great Smoky Mountains National Park, Tennessee, USA, and the implications of climatic changes on vegetation. Environmental Sciences Division publication No. 1111

This report summarizes field work over two summers (1976 and 1977) to relocate, monument and reinventory permanent vegetation plots in the Great Smoky Mountains National Park. These plots were first established by the senior author and R.H. Whittaker in 1959-62. The inventory results are discussed in terms of vegetation changes in high-altitudinal forest ecosystems, in particular the spruce-fir forests, and the factors, climate shift and biotic and abiotic agents, bringing about vegetation change. A second aspect of the report summarizes experience and offers recommendations for establishment of permanent vegetation plots for the purpose of providing a monitoring tool with which to measure long-term ecological change.
Date: March 1, 1978
Creator: Becking, R. W. & Olson, J. S.
Object Type: Report
System: The UNT Digital Library
Determination of performance criteria for high-level solidified nuclear waste from the commercial nuclear fuel cycle: a probabilistic safety analysis (open access)

Determination of performance criteria for high-level solidified nuclear waste from the commercial nuclear fuel cycle: a probabilistic safety analysis

To minimize the radiological risk from the operation of a waste management system for the safe disposal of high-level waste, performance characteristics of the solidified waste form must be specified. The minimum waste form characteristics that must be specified are the radionuclide volatilization fraction, airborne particulate dispersion fraction, and the aqueous dissolution characteristics. The results indicate that the pre-emplacement environs are more limiting in establishing the waste form performance criteria than the post-emplacement environs. The actual values of expected risk are sensitive to modeling assumptions and data base uncertainties. The transportation step appears to be the most limiting in determining the required performance characteristics.
Date: March 30, 1978
Creator: Heckman, R.A.
Object Type: Article
System: The UNT Digital Library
Detection of lower hybrid waves within a plasma by microwave scattering (open access)

Detection of lower hybrid waves within a plasma by microwave scattering

The spatial distribution and intensity of electrostatic waves injected into a hot plasma may be inferred from the scattering of millimeter microwaves. We report measurements on the 30/sup 0/ scattering of 8.6 mm microwaves by a 500 W, 2.45 GHz slow wave excited in a linear plasma by a phased array of two waveguides. From the magnitude of the scattered signal and auxiliary measurements with probes, we infer that a large fraction of the injected power penetrates to the center of the overdense test plasma.
Date: March 1, 1978
Creator: Motley, R. W.; Paoloni, F. J.; Bernabei, S. & Hooke, W. M.
Object Type: Report
System: The UNT Digital Library
Localized corrosion and stress corrosion cracking behavior of austenitic stainless steel weldments containing retained ferrite. Annual progress report, June 1, 1977--March 31, 1978 (open access)

Localized corrosion and stress corrosion cracking behavior of austenitic stainless steel weldments containing retained ferrite. Annual progress report, June 1, 1977--March 31, 1978

Localized corrosion (pitting) experiments have been performed on single-phase austenitic 304 stainless steels and on duplex 304 steels containing 6 to 8% retained delta ferrite as a result of rapid solidification (welding). Experimental variables included thermomechanical treatment, solution pH, chloride concentration and solution temperature.
Date: March 1, 1978
Creator: Savage, W. F. & Duquette, D. J.
Object Type: Report
System: The UNT Digital Library
Kinetics of the ambient temperature dissolution of plutonium metal in sulfamic acid (open access)

Kinetics of the ambient temperature dissolution of plutonium metal in sulfamic acid

The stoichiometry and the kinetics of the ambient temperature dissolution of alpha-phase plutonium in sulfamic acid has been determined. Hydrogen off-gas rates and plutonium concentrations were calculated as functions of time for a variety of dissolving conditions. Calculations show that nominal 2.2 kg Pu buttons (surface area, 171 cm/sup 2/) should yield solutions containing 60 +- 10 g Pu/L after a one-hour dissolving cycle. Hydrogen off-gas rates were calculated to vary from as high as 780 mL of gaseous hydrogen per minute (STP) at the beginning of a dissolving cycle to as low as 150 mL H/sub 2/(g) per min near the end of a dissolving cycle.
Date: March 1, 1978
Creator: Gray, L.W.
Object Type: Report
System: The UNT Digital Library
Methods and calculations for regional, continental, and global dose assessments from a hypothetical fuel reprocessing facility (open access)

Methods and calculations for regional, continental, and global dose assessments from a hypothetical fuel reprocessing facility

The Savannah River Laboratory (SRL) is coordinating an interlaboratory effort to provide, test, and use state-of-the-art methods for calculating the environmental impact to an offsite population from the normal releases of radionuclides during the routine operation of a fuel-reprocessing plant. Results of this effort are the estimated doses to regional, continental, and global populations. Estimates are based upon operation of a hypothetical reprocessing plant at a site in the southeastern United States. The hypothetical plant will reprocess fuel used at a burn rate of 30 megawatts/metric ton and a burnup of 33,000 megawatt days/metric ton. All fuel will have been cooled for at least 365 days. The plant will have a 10 metric ton/day capacity and an assumed 3000 metric ton/year (82 percent online plant operation) output. Lifetime of the plant is assumed to be 40 years.
Date: March 19, 1978
Creator: Schubert, J. F.; Kern, C. D.; Cooper, R. E. & Watts, J. R.
Object Type: Article
System: The UNT Digital Library
Evaluation of ultrafiltration membranes for treating low-level radioactive contaminated liquid waste (open access)

Evaluation of ultrafiltration membranes for treating low-level radioactive contaminated liquid waste

A series of experiments were performed on Waste Disposal Facility (WD) influent using Romicon hollow fiber ultrafiltration modules with molecular weight cutoffs ranging from 2000 to 80,000. The rejection of conductivity was low in most cases. The rejection of radioactivity ranged from 90 to 98%, depending on the membrane type and on the feed concentration. Typical product activity ranged from 7 to 100 dis/min/ml of alpha radiation. Experiments were also performed on alpha-contaminated laundry wastewater. Results ranged from 98 to >99.8%, depending on the membrane type. This yielded a product concentration of less than 0.1 dis/min/ml of alpha radiation. Tests on PP-Building decontamination water yielded rejections of 85 to 88% alpha radiation depending on the membrane type. These experiments show that the ability to remove radioactivity by membrane is a function of the contents of the waste stream because the radioactivity in the wastewater is in various forms: ionic, polymeric, colloidal, and absorbed onto suspended solids. Although removal of suspended or colloidal material is very high, removal of ionic material is not as effective. Alpha-contaminated laundry wastewater proved to be the easiest to decontaminate, whereas the low-level PP-Building decontamination water proved to be the most difficult to decontaminate. Decontamination of …
Date: March 31, 1978
Creator: Koenst, J.W. & Roberts, R.C.
Object Type: Report
System: The UNT Digital Library