Redox reactions involving chromium, plutonium, and manganese in soils (open access)

Redox reactions involving chromium, plutonium, and manganese in soils

Plutonium speciation in soils is discussed. Chromium was selected as a model for studying soil Pu. Similarities between Cr and Pu are pointed out, and a hypotheses concerning Pu speciation in soils is presented. Findings from Cr oxidation studies that may be relevant to the problem of Pu oxidation in soils are discussed. (JGB)
Date: January 1, 1979
Creator: Amacher, M.C. & Baker, D.E.
Object Type: Report
System: The UNT Digital Library
Video monitoring system for enriched uranium casting furnaces (open access)

Video monitoring system for enriched uranium casting furnaces

A closed-circuit television (CCTV) system was developed to upgrade the remote-viewing capability on two oralloy (highly enriched uranium) casting furnaces in the Y-12 Plant. A silicon vidicon CCTV camera with a remotely controlled lens and infrared filtering was provided to yield a good-quality video presentation of the furnace crucible as the oralloy material is heated from 25 to 1300/sup 0/C. Existing tube-type CCTV monochrome monitors were replaced with solid-state monitors to increase the system reliability.
Date: March 1, 1978
Creator: Turner, P. C.
Object Type: Report
System: The UNT Digital Library
Stress corrosion cracking of uranium--niobium alloys (open access)

Stress corrosion cracking of uranium--niobium alloys

The stress corrosion cracking behavior of U-2/sup 1///sub 4/, 4/sup 1///sub 2/, 6 and 8 wt % Nb alloys was evaluated in laboratory air and in aqueous Cl/sup -/ solutions. Thresholds for crack propagation were obtained in these environments. The data showed that Cl/sup -/ solutions are more deleterious than air environments. Tests were also conducted in pure gases to identify the species in the air responsible for cracking. These data showed the primary stress corrodent is water vapor for the most reactive alloy, U-2/sup 1///sub 4/% Nb, while O/sub 2/ is primarily responsible for cracking in the more corrosion resistant alloys, U-6 and 8% Nb. The 4/sup 1///sub 2/% alloy was found to be susceptible in both H/sub 2/O and O/sub 2/ environments.
Date: March 1, 1978
Creator: Magnani, N.J.
Object Type: Report
System: The UNT Digital Library
Selected constituents in the smoke of domestic low tar cigarettes (open access)

Selected constituents in the smoke of domestic low tar cigarettes

Thirty-two brands of domestic commercial low tar and nicotine cigarettes were analyzed for their production of tar, nicotine, nitrogen oxides (as nitric oxide), hydrogen cyanide, acrolein, carbon monoxide and carbon dioxide under standard analytical smoking conditions. Results are compared with published data for certain brands.
Date: December 1, 1977
Creator: Griest, W. H.; Quincy, R. B. & Guerin, M. R.
Object Type: Report
System: The UNT Digital Library
/sup 16/O + /sup 40/Ca inelastic scattering and the elastic scattering wave function (open access)

/sup 16/O + /sup 40/Ca inelastic scattering and the elastic scattering wave function

The /sup 16/O + /sup 40/Ca inelastic scattering has been measured at 60-MeV incident energy, and evidence has been found in support of an explicit coupling between direct and elastic channels. The measurements were extended over a large angular range and in particular to very forward angles. The ratio of cross sections between extreme forward and backward angles proved very useful in studying the underlying reaction mechanism.
Date: January 1, 1977
Creator: Rehm, K.E.; Henning, W.; Erskine, J.R. & Kovar, D.G.
Object Type: Article
System: The UNT Digital Library
Approach to decision modeling for an ignition test reactor (open access)

Approach to decision modeling for an ignition test reactor

A comparison matrix decision model is applied to candidates for a D-T ignition tokamak (TNS), including assessment of semi-quantifiable or judgemental factors as well as quantitative ones. The results show that TNS is mission-sensitive with a choice implied between near-term achievability and reactor technology.
Date: September 30, 1977
Creator: Howland, H.R. & Varljen, T.C.
Object Type: Article
System: The UNT Digital Library
TNS Doublet tokamak ohmic-heating power supply study (open access)

TNS Doublet tokamak ohmic-heating power supply study

Separate abstracts were prepared for each of the six included sections. (MOW)
Date: January 1, 1978
Creator: Rogers, J.D. (comp.)
Object Type: Report
System: The UNT Digital Library
Pilot plant test plan, Task IX: technical support. Industrial Low-Btu Fuel Gas Demonstration-Plant Program (open access)

Pilot plant test plan, Task IX: technical support. Industrial Low-Btu Fuel Gas Demonstration-Plant Program

The objective of the AAG pilot plant operation is to provide process data for the gasification and related sections of the demonstration plant. Since the pilot plant will not operate at the actual pressure of the demonstration plant, it is planned to perform tests at two different pressures to obtain a sound basis for pressure scale-up. Other objectives are listed briefly.
Date: January 1, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Effects of light intensity and PH on photosynthesis in Elodea densa (open access)

Effects of light intensity and PH on photosynthesis in Elodea densa

None
Date: August 1, 1975
Creator: Weber, J.A. & Gates, D.M.
Object Type: Article
System: The UNT Digital Library
Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report. Appendix A: mission analysis and performance specification studies. Volume I (open access)

Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report. Appendix A: mission analysis and performance specification studies. Volume I

Studies are described which were performed for the Near Term Hybrid Vehicle program to determine passenger car usage patterns and to correlate these trip mission characteristics with vehicle design and performance specifications. (LCL)
Date: April 20, 1979
Creator: Traversi, M. & Barbarek, L.A.C.
Object Type: Report
System: The UNT Digital Library
Office of Waste Isolation progress report, December 1977 (open access)

Office of Waste Isolation progress report, December 1977

This document reports progress on the OWI's portion of the National Waste Terminal Storage (NWTS) program. It comprises project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. They are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs. (DLC)
Date: January 31, 1976
Creator: Zerby, C.D.
Object Type: Report
System: The UNT Digital Library
Advanced /sup 90/Sr space power supply. 250 watt dynamic system (open access)

Advanced /sup 90/Sr space power supply. 250 watt dynamic system

None
Date: September 6, 1973
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Intermediate-depth geothermal temperature study. Gradient holes: 11-33 and 63-33, Soda Lake, NV (open access)

Intermediate-depth geothermal temperature study. Gradient holes: 11-33 and 63-33, Soda Lake, NV

During 1979, Chevron Resources Company drilled two 2000 ft holes near Soda Lake in the Nevada Carson Sink area to obtain subsurface data for inclusion in the US Department of Energy's Northern Basin and Range geothermal reservoir assessment program. Drilling information together with detailed lithologic, geophysical and temperature log data were compiled for each hole and is summarized in this report. Maximum stabilized temperatures of 297/sup 0/F and 367/sup 0/F were encountered at total depth in each of the holes, respectively.
Date: October 1, 1979
Creator: Hill, D.G.
Object Type: Report
System: The UNT Digital Library
DOE role in nuclear policies and programs: official transcript of public briefing. Addendum December 13, 1977, Washington, D. C (open access)

DOE role in nuclear policies and programs: official transcript of public briefing. Addendum December 13, 1977, Washington, D. C

A total of 24 questions were read into the official record at the public briefing on nuclear policies and programs. The answers published were researched and written by personnel of DOE's Office of Energy Research, Office of Energy Technology, and the Secretary's Office. A few questions were sent to the Nuclear Regulatory Commission for review and for preparation of answers.
Date: February 1, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Heavy mass states (open access)

Heavy mass states

The indirect evidence for the production of a heavy lepton and direct evidence for the product of a new hadronic state or states in proton-proton interactions is considered for the interpretation requiring the existence of two more leptons and two new quarks. It is shown that such a picture is consistent and in good agreement with existing data. The new structure is located at M = 9.54 GeV/c/sup 2/ and is much wider than the experimental resolution. Also it is asymmetric, suggesting the presence of several resonances. 7 references. (JFP)
Date: August 23, 1977
Creator: Paschos, E. A.
Object Type: Article
System: The UNT Digital Library
Compatibility testing of vitrified waste forms (open access)

Compatibility testing of vitrified waste forms

An experimental program to evaluate candidate metals for use in the fabrication of canisters for long-term storage of vitrified radioactive wastes is described. The long-term compatibility of the candidate metal both with the contained vitrified radioactive waste and with the external environments expected in possible final storage locations will be determined. These tests involve heating combinations of waste forms and canister metals in intimate contact for up to 50,000 hr to accelerate any reactions that occur.
Date: March 6, 1978
Creator: Rankin, W.N.
Object Type: Article
System: The UNT Digital Library
Cryogenic supplies for the TFTR neutral beam line cryopanels (open access)

Cryogenic supplies for the TFTR neutral beam line cryopanels

Cryocondensing panels will be used for the Neutral Beam Lines of the TFTR to satisfy a pumping speed requirement of 2.5 x 10/sup 6/ l/s. The cryocondensing panels are fed by liquid helium (LHe), boiling at selectable temperatures of 4.5/sup 0/K or 3.8/sup 0/K. Liquid nitrogen (LN/sub 2/) panels and chevrons thermally shield the LHe panel. The closed-loop LHe supply system and the open loop LN/sub 2/ system are discussed. The helium refrigerator of minimum 1070-W capacity, together with its distribution system, and the nitrogen distribution system in the ton/hour LN/sub 2/ range is presented. Problems and their solutions in connection with the LHe system, including the distribution over a distance of 500 feet of large quantities of liquid/gas mixtures with load variations over the range of about 3 : 1, and the economies of various types of distribution lines (passive, pumped, shielded, combined), are described. The system design passed the preliminary phase. Design features and auxiliary equipment to assure dispersion of large quantities of nitrogen into the atmosphere and to permit operation under degraded cryogenic helium refrigerator performance are also discussed in Design Considerations.
Date: January 1, 1977
Creator: Pinter, G.
Object Type: Article
System: The UNT Digital Library
TCT hybrid preconceptual blanket design studies (open access)

TCT hybrid preconceptual blanket design studies

The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal divertor. The blanket concept selected by PPPL consists of a neutron multiplying converter region, containing natural Uranium Molybdenum (U-Mo) slugs followed by a fuel burning blanket region of molten salt containing PuF/sub 3/. PNL analyzed this concept to determine its structural, thermal and hydraulic performance characteristics. An adequate first wall cooling method was determined, utilizing low pressure water in a double wall design. A conceptual layout of the converter region tubes was performed, providing adequate helium cooling and the desired movement of U-Mo slugs. A thermal hydraulic analysis of the power-producing blanket regions indicated that either more helium coolant tubes are needed or the salt must be circulated to obtain adequate heat removal capability.
Date: January 1, 1978
Creator: Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.
Object Type: Report
System: The UNT Digital Library
Discussion: ''toughness variations during the tempering of a plain carbon martensitic steel'' by J. E. King, R. F. Smith and J. F. Knott. Retained austenite and transgranular tempered martensite embrittlement (open access)

Discussion: ''toughness variations during the tempering of a plain carbon martensitic steel'' by J. E. King, R. F. Smith and J. F. Knott. Retained austenite and transgranular tempered martensite embrittlement

Discussion is presented to substantiate, clarify and reinterpret some of the results of the above authors for the existence and origin of tempered martensite embrittlement (TME) in relation to retained austenite, with reference to the experimental steels worked at LBL for the past several years.
Date: June 1, 1977
Creator: Rao, B.V.N. & Thomas, G.
Object Type: Article
System: The UNT Digital Library
Thorium fuel cycles for LWRs: fuel diversion assessments and recycle requirements (open access)

Thorium fuel cycles for LWRs: fuel diversion assessments and recycle requirements

A number of fuel cycles have been proposed for evaluation in the nonproliferation alternative systems assessment program. Among these systems are light water reactors (LWR) operating on the thorium-uranium cycle or the plutonium-thorium cycle either inside or outside energy centers. These proposals support the President's nuclear power policy of accelerating research into alternative fuel cycles that do not permit direct access to materials usable for nuclear weapons but still retain the benefits of nuclear power. Reprocessing and refabrication (often referred to as the ''back cycle'') constitute a portion of the overall fuel cycle and represent potential access points to fissionable materials, which, in many cases, may be in a rather attractive form for diversion. These operations for LWR thorium-uranium and plutonium-thorium fuels were analyzed to assess and rate the diversion or proliferation potential of each major operation. Reprocessing and refabrication evaluations per se constitute insufficient data for rating the acceptability of an entire fuel cycle and must be considered along with reactor analysis, environmental data, resource utilization, and political factors. Each back cycle operation has been evaluated according to needed development, material location, material description, convertibility and radiation hazard. Needed development relates to the state of the art of the …
Date: January 1, 1978
Creator: Carter, W. L.; Rainey, R. H. & Johnson, D. R.
Object Type: Article
System: The UNT Digital Library
First order study for an iron core OH system for TNS (open access)

First order study for an iron core OH system for TNS

A simple comparison has been made between an air core and an iron core ohmic heating system for a particular device, and it was shown that the peak power requirements can be substantially reduced by the use of an iron core to power levels handled by industry today. It was also shown that for an ohmic heating system initiated plasma that the cost of the iron core ohmic heating power system (iron core, dual rectifier, and DC switch) is less than the cost for a subset of the power system for an air core system (dual rectifier and DC switch). There is considerable work being done on other methods of initiating the plasma none of which seem to be incompatible with the use of an iron core system.
Date: January 1, 1977
Creator: Ballou, J. K. & Schultz, J.
Object Type: Article
System: The UNT Digital Library
Design, development, and demonstration of a promising integrated appliance. Phase I: design. Final report (open access)

Design, development, and demonstration of a promising integrated appliance. Phase I: design. Final report

The combination or integration of appliances for the economical recovery of energy which is normally wasted during the operation of heating systems, air conditioners, water heaters, stoves, clothes washers and driers, and refrigerators in homes and commercial buildings was studied. The potential energy savings achievable by using waste heat from one appliance as heat input to another, e.g., water heaters, was estimated, and the economic benefit to the consumer calculated. Six integrated appliance systems, all involving waste heat utilization to augment water heating were identified as economically feasible with a maximum cost payback period of 3.5 y in residential buildings and 5.0 y for commercial buildings. These included heat recovery from furnaces, air conditioners, commercial ranges, heat in water drains in homes, and heat in water drains in commercial buildings. The first three are the most promising. A program to demonstrate the performance of these three integrated appliance systems and to further their commercialization is recommended. (LCL)
Date: September 1, 1977
Creator: Lee, W. D.; Lawrence, W. T. & Wilson, R. P.
Object Type: Report
System: The UNT Digital Library
Experimental program to validate analyses of accelerator breeder concepts (open access)

Experimental program to validate analyses of accelerator breeder concepts

The concept of using high-energy particle accelerators to produce neutrons for converting fertile material to fissile is over 25 years old. It is only relatively recently that accelerator design has progressed to a point where the operation approaches commercial viability. Critical unknowns in the concept were identified in a detailed study of specic configurations. Experiments to elucidate these unknowns in a timely manner using existing material and facilities are defined and identified. Basic measurements are described to evaluate effects of the primary particle beam and resulting secondary particles in massive assemblies of most materials of interest.
Date: January 1, 1977
Creator: Talbert Jr., W. L.; Russell, G. J. & Malenfant, R. E.
Object Type: Article
System: The UNT Digital Library
Thermal properties. Period covered, April--June 1975. [Chemical reactivity data for PBX 9404 and PETN, chemical explosives] (open access)

Thermal properties. Period covered, April--June 1975. [Chemical reactivity data for PBX 9404 and PETN, chemical explosives]

None
Date: January 1, 1975
Creator: Myers, L.C.
Object Type: Report
System: The UNT Digital Library