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in subjects: "Years Living Radioisotopes"

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Nuclear design of fast hybrid blankets

The objective of this presentation is to: (1) present the physical motivation for fusion-fission hybrids, (2) outline design considerations for hybrid blankets, and (3) discuss the nuclear performance potential of hybrid blankets.

Date: January 23, 1978

Creator: Lee, J. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Tritium Systems Test Assembly: objectives and design

The principal program objectives for TSTA are: (1) to develop and demonstrate the fuel cycle for fusion power reactors; (2) to develop and test environmental and personnel protective systems; (3) to develop, test, and qualify equipment for tritium service; (4) to provide a final demonstration facility that could be directly copied for a D-T burning fusion machine; (5) to demonstrate long-term reliability of components; (6) to demonstrate long-term safe handling of tritium with no major releases… more

Date: January 1, 1980

Creator: Anderson, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Use of miniature C-14 counters in dating and authentication in the museum

Curators often do not understand the basis for the C-14 method of age determination and its limitations. Purpose of this paper is to describe the underlying principles, and how these must influence the interpretation of the radiocarbon measurement of a museum specimen in terms of age. Several techniques for that measurement are described briefly, focussing on the miniature proportional counters that were developed for the Smithsonian Institution, and three museum problems are described which we… more

Date: January 1, 1983

Creator: Harbottle, G.; Sayre, E.V. & Stoenner, R.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Safety considerations in the design of the Fusion Engineering Device

The US Department of Energy (DOE) regulations and guidelines for radiation protection have been reviewed and are being applied to the device design. Direct radiation protection is provided by the device shield and the reactor building walls. Radiation from the activated device components and the tritium fuel is to be controlled with shielding, contamination control, and ventilation. The potential release of tritium from the plant has influenced the selection of reactor building and plant design… more

Date: January 1, 1983

Creator: Barrett, R.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tritium technology review

The methods used in recovering, containing and controlling tritium in fusion reactor systems are the subject of the paper. Safety, cost, and breeding needs for tritium control are outlined.

Date: January 1, 1985

Creator: Finn, P.A. & Sze, D.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Tritium control at the Tritium Systems Test Assembly

The Tritium Systems Test Assembly (TSTA) is a computer-controlled facility designed to mock up full-scale the deuterium-tritium fuel cycle of next-generation tokamak fusion test reactors. Such reactors will use or build on the experience and technologies of the TSTA and other engineering facilities. The TSTA is presently under construction at the Los Alamos Scientific Laboratory and will be fully operational in 1982.

Date: January 1, 1980

Creator: Jalbert, R. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Decay properties of nuclei at the end of the periodic system

Recent studies of nuclear mass models show that it is essential to account for the Coulomb redistribution energy when calculating the nuclear potential energy in the heavy-element region. Results obtained by use of a mass model that includes Coulomb redistribution effects on analyzed. Q values of {alpha} and {beta} decay are calculated. Half-lives for {alpha} decay are estimated by use of the Viola-Seaborg systematics. For EC, {beta}{sup +} decay and {beta}{sup {minus}} decay, half-lives are ca… more

Date: January 24, 1992

Creator: Moeller, P. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)) & Nix, J.R. (Los Alamos National Lab., NM (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Design of the waveguide for microwave heating of solid lithium ceramic blankets

A description is given of the design of a dielectric-loaded waveguide for thermohydraulic testing of solid ceramic tritium breeder material in a non-nuclear environment. The dielectric-loaded waveguide provides uniform heating over module surfaces that would face a fusion reactor plasma and simulates the exponential power decay characteristic of the neutron flux over the high power region of the blankets. A 200-MHz design suitable for modules with cross section of up to 20 x 40 cm is presented.

Date: January 1, 1985

Creator: Kustom, R.L.; Fendley, P. & Tidona, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Radionuclide detection by inductively coupled plasma mass spectrometry: A comparison of atomic and radiation detection method

Radionuclide detection by mass spectrometric techniques offers inherent advantages over conventional radiation detection methods. Since radionuclides decay at variable rates (half-lives) and via various nuclear transformations (i.e. emission of alpha, beta, and/or gamma radiation) their determination via radiation detection depends not only on decay systematics but also on detector technology. Radionuclide detection by direct atom measurement, however, is dependent only on technique sensitivity… more

Date: April 1, 1991

Creator: Smith, M. R.; Wyse, E. J. & Koppenaal, D. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Tritium containment costs at Lawrence Livermore Laboratory

Lawrence Livermore Laboratory has improved tritium-handling systems to prevent significant releases of tritium to the environment. Two methods of lowering the costs of such systems have been found: maintaining design flexibility and combining the best features of single- and double-containment designs.

Date: June 15, 1979

Creator: Shaw, J.F. & Alire, R.M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Tritium-containment systems: a tradeoff study

Various design parameters are evaluated that affect the performance of tritium-containment systems for fusion reactors. Our study included a review of such parameters as tritium forms, impurities, catalysts, adsorbents, getters, and as low as reasonably achievable principles. We organized these schemes, which can be considered for treating either air or inert atmospheres, so one could easily make orderly choices and tradeoffs for optimum performance. The relationships examined involved purifica… more

Date: December 18, 1978

Creator: Folkers, C.L. & Cena, R.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Development of a quality-assurance program for the Tritium Systems Test Assembly

A quality assurance program was developed for TSTA with the attempt in mind to satisfy the developmental nature of the project. Numerous reviews replace strict guidelines because guidelines are one of the objectives of the project, not a basis for it. The reviews assure adequate technical consideration and avoid unilateral decisions. Other major requirements of the program plan include interfacing with another quality assurance organization, the assignment of responsibilities, and instructions … more

Date: January 1, 1981

Creator: Minor, R.C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Results of tritium tests performed on Sandia Laboratories decontamination system

The Tritium Research Laboratory (TRL), a facility for performing experiments using gram amounts of tritium, became operational on October 1, 1977. As secondary containment, the TRL employs sealed glove boxes connected on demand to two central decontamination systems, the Gas Purification System and the Vacuum Effluent Recovery System. Performance tests on these systems show the tritium removal systems can achieve concentration reduction factors (ratio of inlet to exhaust concentrations) much in… more

Date: May 1, 1978

Creator: Gildea, P. D.; Wall, W. R. & Gede, V. P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Primordial Pb, radiogenic Pb and lunar soil maturity

The soil maturity index I/sub s//FeO does not apply to either /sup 204/Pb/sub r/ or C/sub hyd/; both are directly correlated with the submicron Fe/sup 0/(I/sub s/) content. They act as an index of soil maturity which is independent of soil composition. In contrast to primordial Pb, radiogenic Pb is lost during soil maturation. Radiogenic Pb is present in mineral grains and may be lost by solar wind sputtering (or volatilization) and not resupplied. /sup 204/Pb coating grain surfaces acts as a r… more

Date: January 1, 1978

Creator: Reed, George W., Jr. & Jovanovic, Stanka

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Safety analysis report: packages. 232-H Byproduct Trailer (packaging of radioactive material). Final report. [Helium containing some tritium]

Helium containing some tritium is shipped at low pressure in banks of cylinders mounted on a truck trailer in compliance with 49 CFR 178.350, Specification 7A. The shipping package is not a radiological hazard under normal or accident conditions.

Date: December 1, 1975

Creator: Chalfant, G.G. (comp.)

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Results for f[sub B] and f[sub D] at [beta] = 6. 3

We have computed the decay constants for the B and D mesons, using quenched lattices at [beta] = 6.3, by interpolating between the static approximation of Eichten and the conventional ( heavy'' Wilson fermion) method. A more careful treatment of the static result using better sources with longer time-displacements and a modification to the Wilson quark normalization to correct approximately for lattice effects in the large-am regime have led to the elimination of the large discrepancy between t… more

Date: January 1, 1992

Creator: Bernard, C. (Washington Univ., St. Louis, MO (United States). Dept. of Physics); Labrenz, J. (Washington Univ., Seattle, WA (United States). Dept. of Physics) & Soni, A. (Brookhaven National Lab., Upton, NY (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Tritium monitoring within the reactor hall of a DT fusion reactor

Monitoring the reactor hall atmosphere of DT-fueled fusion reactors will probably be performed with conventional ion chamber and proportional counter instruments modified as necessry to deal with the background radiation. Background includes external neutron and gamma radiation and internal beta-gamma radiation from the activated atmosphere. Although locating instruments in remote areas of the reactor hall and adding local shielding and electronic compensation may be feasible, placing the instr… more

Date: January 1, 1983

Creator: Jalbert, R. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

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Carbon and carbon-14 in lunar soil 14163

Carbon is removed from the surface of lunar soil 14163 size fractions by combustions at 500 and 1000/sup 0/C in an oxygen stream and the carbon contents and the carbon-14 activities are measured. The carbon contents are inversely correlated with grain size. A measured carbon content of 198 ppM for bulk 14163, obtained by combining the size fraction results, is modified to 109 +- 12 ppM by a carbon contamination correction. This value is in accord with a previous determination, 110 ppM, for bulk… more

Date: January 1, 1981

Creator: Fireman, E.L. & Stoenner, R.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Cost of tritium bred in a critical fission reactor

Elementary equations related to the ''six-factor'' formula for criticality are used to derive an expression for the cost of tritium, bred in a fission reactor, in terms of the cost of fissile material. Reasonable parameters give a value about two-thirds of that usually quoted (80 times the price of fissile) for fusion-fission reactor self-bred tritium. However, the handling costs and hazards associated with large-scale LWR tritium production are not assessed.

Date: April 1, 1977

Creator: Price, W. G. Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Chromatographic measurement of hydrogen isotopic and permanent gas impurities in tritium

This paper describes a gas chromatograph that was designed for dedicated analysis of hydrogen isotopic and permanent gas impurities in tritium and tritium-deuterium mixtures. The instrument that was developed substantially improved the accuracy and precision of hydrogen isotopic analysis in the 20 ppM to one mole percent range as compared with other analytical methods. Several unique design features of the instrument were required due to the radiation and isotopic exchange properties of the tri… more

Date: June 4, 1976

Creator: Warner, David K.; Kinard, Christopher & Bohl, Donald C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Temperature-dependent ordinary and thermal diffusion of hydrogen isotopes through thermonuclear reactor components

To permit more accurate calculations of tritium permeation for design purposes, theoretical expressions for quasiunidirectional ordinary diffusion of hydrogen isotopes through nonisothermal plane, cylindrical shell, and spherical shell barriers are presented. Arrhenium-type dependence of mass diffusivity on temperature and steady-state constant-thermal-conductivity temperature gradients through the barriers are considered. Analyses that consider thermal diffusion with both constant and temperat… more

Date: September 1, 1976

Creator: Pendergrass, J. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Tritium Systems Test Facility

This TSTF proposal has two principal objectives. The first objective is to provide by mid-FY 1981 a demonstration of the fuel cycle and tritium containment systems which could be used in a Tokamak Experimental Power Reactor for operation in the mid-1980's. The second objective is to provide a capability for further optimization of tritium fuel cycle and environmental control systems beyond that which is required for the EPR. The scale and flow rates in TSTF are close to those which have been pr… more

Date: February 22, 1978

Creator: Cafasso, F. A.; Maroni, V. A.; Smith, W. H.; Wilkes, W. R. & Wittenberg, L. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Development of a two-stage light gas gun to accelerate hydrogen pellets to high speeds for plasma fueling applications

The development of a two-stage light gas gun to accelerate hydrogen isotope pellets to high speeds is under way at Oak Ridge National Laboratory. High velocities (>2 km/s) are desirable for plasma fueling applications, since the faster pellets can penetrate more deeply into large, hot plasmas and deposit atoms of fuel directly in a larger fraction of the plasma volume. In the initial configuration of the two-stage device, a 2.2-l volume (/<=/55-bar) provides the gas to accelerate a 25.4-mm-diam… more

Date: January 1, 1988

Creator: Combs, S. K.; Milora, S. L.; Foust, C. R.; Gouge, M. J.; Fehling, D. T. & Sparks, D. O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fabrication of /sup 252/Cf medical sources

Three types of neutron sources are made, i.e., seeds, afterloading cells, and applicator tubes. All sources are made with a Pd--Cf/sub 2/O/sub 3/ cermet wire core with Pt--Ir cladding. The seed has a 0.032 in. dia and is 0.240 in. long, with an active length of 0.160 in. The average content of each seed is 0.4 to 0.5 ..mu..g /sup 252/Cf. The double encapsulated afterloading cells are 0.040 in. in dia and 0.705 in. or 0.905 in. long. The active length is 0.590 in. or 1.20 in. The /sup 252/Cf con… more

Date: January 1, 1978

Creator: Lathrop, R. R.; Thompson, G. & Curlee, W. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department