59 Matching Results

Search Results

Advanced search parameters have been applied.
in creator/contributor: "Maroni, V. A."  
Results: 1 - 24 next
open access

Control of tritium permeation through fusion reactor strucural materials

Description: The intention of this paper is to provide a brief synopsis of the status of understanding and technology pertaining to the dissolution and permeation of tritium in fusion reactor materials. The following sections of this paper attempt to develop a simple perspective for understanding the consequences of these phenomena and the nature of the technical methodology being contemplated to control their impact on fusion reactor operation. Considered in order are: (1) the occurrence of tritium in the … more
Date: January 1, 1978
Creator: Maroni, V.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Tritium processing and containment technology for fusion reactors: perspective and status

Description: This paper reviews the status of selected tritium processing and containment technologies that will be required to support the development of the fusion energy program. Considered in order are the fuel conditioning and recycle systems, the containment and cleanup systems, the blanket processing systems, and two unique problems relating to tritium interactions in neutral beam injectors and first wall coolant circuits. The major technical problem areas appear to lie in the development of (1) high… more
Date: January 1, 1976
Creator: Maroni, V. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analysis of tritium distribution and leakage characteristics for two fusion reactor reference designs

Description: From 5th sympostum on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). Results of analyses of the tritium distribution and leakage characteristics for two current fusion power reactor designs -the Princeton Reference Model Tokamak and the LASL/ANL Reference Theta Pinch Reactor--are presented and compared. The philosophy of the model used in these analyses is discussed, and the computer code, developed to carry out the calculations, is described. Consideration is… more
Date: January 1, 1973
Creator: Maroni, V.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

First-wall, blanket, and shield engineering test program for magnetically confined fusion power reactors

Description: The key engineering areas identified for early study relate to FW/B/S system thermal-hydraulics, thermomechnics, nucleonics, electromagnetics, assembly, maintenance, and repair. Programmatic guidance derived frm planning exercises involving over thirty organizations (laboratories, industries, and universities) has indicated (1) that meaningful near term engineering testing should be feasible within the bounds of a modest funding base, (2) that there are existing facilities and expertise which c… more
Date: January 1, 1980
Creator: Maroni, V.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal hydraulic analyses of two fusion reactor first wall/blanket concepts

Description: A comparative study has been made of the thermal hydraulic performance of two liquid lithium blanket concepts for tokamak-type reactors. In one concept lithium is circulated through 60-cm deep cylindrical modules oriented so that the module axis is parallel to the reactor minor radius. In the other concept helium carrying channels oriented parallel to the first wall are used to cool a 60-cm thick stagnant lithium blanket. Paralleling studies were carried out wherein the thermal and structural p… more
Date: January 1, 1977
Creator: Misra, B. & Maroni, V.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analysis of the separation of protium from blanket tritium-product streams

Description: The case is considered in which the blanket product stream has been purified to the point where only protium, tritium, and a small quantity of deuterium remain. A cryogenic distillation cascade concept developed specifically to handle this enrichment problem is shown. The concept is based on a series of distillation columns and equilibrators capable of producing a protium-rich stream containing less than 1000 appm T and a tritium-rich stream containing less than 2000 appm H. It is envisioned th… more
Date: July 1, 1981
Creator: Misra, B. & Maroni, V.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Multicomponent isotopic separation and recirculation analysis. [MISRA]

Description: A digital computer program for design of multicomponent distillation columns has been developed based on an exact method of solution of the governing equations. Although this computer program was developed for enrichment of the spent fuels from presently conceived tokamak-type fusion power reactors by cryogenic distillation, the program can be used for the design of any multicomponent distillation column, provided, of course, the necessary thermodynamic and phase equilibrium data are available.… more
Date: January 1, 1976
Creator: Misra, B. & Maroni, V. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Isotopic enrichment of plasma exhausts from controlled thermonuclear reactors by cryogenic distillation

Description: The feasibility of recycling the spent fuels from presently conceived tokamak-type power reactors via cryogenic distillation has been analyzed. As an essential step in analyzing complex mixtures consisting of the six isotopomeric forms of molecular hydrogen in widely varying ranges of concentrations, computer simulation of multicomponent distillation was carried out using an exact method of solution of the governing equations. Two distinct fuel injection schemes were analyzed using a six-column… more
Date: January 1, 1976
Creator: Misra, B. & Maroni, V. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Analysis of the October 5, 1979 Lithium Spill and Fire in the Lithium Processing Test Loop

Description: On October 5, 1979, the Lithium Processing Test Loop (LPTL) developed a lithium leak in the electromagnetic (EM) pump channel, which damaged the pump, its surrounding support structure, and the underlying floor pan. A thorough analysis of the causes and consequences of the pump failure was conducted by personnel from CEN and several other ANL divisions. Metallurgical analyses of the elliptical pump channel and adjacent piping revealed that there was a significant buildup of iron-rich crystallit… more
Date: December 1981
Creator: Maroni, V. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Applications of molecular spectroscopy methods to the study of metal dusting corrosion.

Description: The interrogation of molecular vibrations in crystalline and amorphous solids by Raman and infrared spectroscopy methods can provide a wealth of revealing information concerning the composition, morphology, and spatial distribution of the extant phases. When these measurements are made in situ, such as during processes taking place in extreme environments (e.g., elevated temperature and pressure, oxidizing or reducing), where phases are evolving and/or dissipating, it is also possible to derive… more
Date: March 11, 2002
Creator: Maroni, V. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Initial progress in the first wall, blanket, and shield Engineering Test Program for magnetically confined fusion-power reactors

Description: The first wall/blanket/shield (FW/B/S) Engineering Test Program (ETP) progressed from the planning stage into implementation during July, 1981. The program, generic in nature, comprises four Test Program Elements (TPE's), the emphasis of which is on defining the performance parameters for the Fusion Engineering Device (FED) and the major fusion device to follow FED. These elements are: (1) nonnuclear thermal-hydraulic and thermomechanical testing of first wall and component facsimiles with emph… more
Date: October 1, 1981
Creator: Herman, H.; Baker, C. C. & Maroni, V. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal hydraulic and power cycle analysis of liquid lithium blanket designs

Description: Thermal hydraulic and power cycle analyses were performed for the first-wall and blanket systems of tokamak-type fusion reactors under a typical set of design and operating conditions. The analytical results for lithium-cooled blanket cells show that with stainless steel as construction material and with no divertor present, the maximum allowable neutron wall loading is approximately 2 MW/m/sup 2/ and is limited by thermal stress criteria. With vanadium alloy as construction material and no div… more
Date: January 1, 1977
Creator: Misra, B.; Stevens, H.C. & Maroni, V.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of Tritium Technology for the United States Magnetic Fusion Energy Program

Description: Tritium technology development for the DOE fusion program is taking place principally at three laboratories, Argonne National Laboratory, Los Alamos Scientific Laboratory, and Mound Facility. This paper will review the major aspects of each of the three programs and look at aspects of the tritium technology being developed at other Laboratories within the United States.
Date: January 1, 1980
Creator: Anderson, J. L.; Wilkes, W. R. & Maroni, V. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Study of nanophase TiO/sub 2/ grain boundaries by Raman spectroscopy

Description: Raman spectra have been recorded for as-consolidated nanophase TiO/sub 2/ samples with differing grain sizes and on samples annealed in air at a variety of temperatures up to 1273 K. The nanophase samples with the smallest grain size, about 12 nm average diameter, could have 15-30% of their atoms in grain boundaries; nevertheless, the strong Raman-active lines representative of the rutile structure were found to dominate all of the observed spectra, independent of grain size and annealing treat… more
Date: January 1, 1989
Creator: Melendres, C.A.; Narayanasamy, A.; Maroni, V.A. & Siegel, R.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Solution behavior of hydrogen isotopes and other non-metallic elements in liquid lithium

Description: Results of experimental studies to measure selected thermodynamic properties for systems of lithium with non-metallic elements are reported. Investigations of the Li-H, Li-D, and Li-T systems have led to the elucidation of the dilute solution behavior and the H/D/T isotope effects. In the case of the Li-H and Li-D systems, the principal features of the respective phase diagrams have been delineated. The solubility of Li-D in liquid lithium has been measured down to 200/sup 0/C. The solubility o… more
Date: January 1, 1976
Creator: Maroni, V. A.; Calaway, W. F.; Veleckis, E. & Yonco, R. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Lead-rich phases in partially processed Ag/Bi-2223 composite conductors

Description: The occurrence, composition, and melting behavior of lead-rich phases detected during the thermal processing of Ag/Bi-2223 composite conductors have been investigated by a combination of transmission electron microscopy (TEM), energy dispersive analysis (EDS), x-ray diffraction, differential thermal analysis, and Raman spectroscopy. A (Bi,Pb)-Sr-Ca-Cu-O composition with {open_quotes}4112{close_quotes} metal atom stoichiometry and Pb{approx_equal}Bi was detected during TEM/EDS examinations of pa… more
Date: February 1996
Creator: Luo, J. S.; Merchant, N. & Maroni, V. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The application of imaging Raman microscopy to high temperature superconducting ceramics

Description: An imaging Raman microscope is used to detect and image phases in high-{Tc} superconductor powders, pellets, and silver-sheathed composites. The procedure involves the following series of measurements: (1) spot-focused (< 5 {micro}m) Raman microprobe spectral measurements on isolated crystallites; (2) defocused (3 50 {micro}m) Raman microprobe spectral measurements on isolated crystallites and surrounding area; (3) Raman spatial images of each band in the defocused Raman spectrum; and (4) spot-… more
Date: December 31, 1995
Creator: Maroni, V.A.; Wu, K. & Fischer, A.K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The investigation of phase evolution in composite ceramic superconductors using Raman microscopy techniques

Description: Raman microspectroscopy and imaging techniques have been used to investigate key mechanistic features that influence the formation of layered Bi- and Tl-based superconducting phases during the thermal treatment employed to produce BSCCO and TBCCO composite conductors. Seminal information gained from these studies includes the location of lead-rich nonsuperconducting second phases (NSPS) and the identification of the constituent phases in certain NSP agglomerations that tend to resist dissipatio… more
Date: December 23, 1999
Creator: Maroni, V. A.; Fischer, A. K. & Wu, K. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

TSOAK-M1 : a Computer Code to Determine Tritium Reaction/Adsorption/Release Parameters from Experimental Results of Air-Detritiation Tests

Description: A computer code has been developed which permits the determination of tritium reaction (T2 to HTO)/adsorption/release and instrument correction parameters from enclosure (building) - detritiation test data. The code is based on a simplified model which treats each parameter as a normalized time-independent constant throughout the data-unfolding steps. Because of the complicated four-dimensional mathematical surface generated by the resulting differential equation system, occasional local-minima… more
Date: 1979?
Creator: Land, Robert H.; Land, Robert H.; Maroni, V. A. & Minkoff, Michael
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen