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Analysis of the sensitivity of spectrum-average cross sections to individual characteristics of differential excitation functions

Description: A simple procedure for analyzing the sensitivity of computed spectrum-average cross sections to detailed properties of excitation functions for threshold nuclear reactions commonly used in reactor dosimetry is described. This procedure is shown to be useful in identifying specific needs for improved differential data and as a tool to be employed in performing evaluations. Several examples are presented to illustrate the subject matter.
Date: March 1, 1977
Creator: Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast neutron radiative capture cross section of /sup 232/Th. [30 keV to 2. 5 MeV]

Description: The /sup 232/Th(n,..gamma..) cross section was measured between 30 keV and 2.5 MeV. A large liquid scintillator was used to measure the shape of the cross section relative to Au(n,..gamma..) between 58 keV and 850 keV. The activation technique was used in measurements at 30 keV relative to Au(n,..gamma..) and above 240 keV relative to /sup 235/U(n,f). The activation results were utilized to normalize the shape data. The results agree well with recent experimental data by Lindner et al. and are … more
Date: March 1, 1978
Creator: Poenitz, W. P. & Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mechanical Design and Thermal Hydraulic Considerations for Self-Cooled Lithium-Lead Blanket

Description: Liquid lithium-lead eutectic alloy (17 at % Li-83 at % Pb, referred to herein as Li-Pb) is currently being considered as a candidate breeding material for fusion reactors. Some important considerations in the design of a Li-Pb blanket are compatibility with the structure, tritium containment and recovery, and safety. Additional design complexities arise because of the high density of Li-Pb, the relatively high melting temperature (235/sup 0/C), and the high tritium over-pressure associated with… more
Date: March 1, 1983
Creator: Misra, B.; Smith, D. L.; Burk, R. C. & Morgan, G. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluated nuclear-data file for niobium

Description: A comprehensive evaluated nuclear-data file for elemental niobium is provided in the ENDF/B format. This file, extending over the energy range 10/sup -11/-20 MeV, is suitable for comprehensive neutronic calculations, particulary those dealing with fusion-energy systems. It also provides dosimetry information. Attention is given to the internal consistancy of the file, energy balance, and the quantitative specification of uncertainties. Comparisons are made with experimental data and previous ev… more
Date: March 1, 1985
Creator: Smith, A. B.; Smith, D. L. & Howerton, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Influence of temperature and lithium purity on corrosion of ferrous alloys in a flowing lithium environment

Description: Corrosion data have been obtained on ferritic HT-9 and Fe-9Cr-1Mo steel and austenitic Type 316 stainless steel in a flowing lithium environment at temperatures between 372 and 538/sup 0/C. The corrosion behavior is evaluated by measurements of weight loss as a function of time and temperature. A metallographic characterization of materials exposed to a flowing lithium environment is presented.
Date: March 1, 1986
Creator: Chopra, O. K. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear data and measurements series: Some comments on the effects of long-range correlations in covariance matrices for nuclear data

Description: Attention is called to the considerable sensitivity of many uncertainty calculations to the magnitude of the long-ranged correlations which appear in covariance matrices. If such correlations do exist, they must be included in order to properly assess the impact of the uncertainties in the data. If, however, certain assumed long-range correlations are unrealistic, then analyses involving such correlation information are almost certain to produce misleading results. The issue is discussed in gen… more
Date: March 1, 1987
Creator: Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A vector model for error propagation

Description: A simple vector model for error propagation, which is entirely equivalent to the conventional statistical approach, is discussed. It offers considerable insight into the nature of error propagation while, at the same time, readily demonstrating the significance of uncertainty correlations. This model is well suited to the analysis of error for sets of neutron-induced reaction cross sections. 7 refs., 1 fig.
Date: March 1, 1989
Creator: Smith, D. L. & Geraldo, L. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and testing of a deuterium gas target assembly for neutron production via the H-2(d,n)He-3 reaction at a low-energy accelerator facility

Description: This report describes the development and testing of a deuterium gas target intended for use at a low-energy accelerator facility to produce neutrons for basic research and various nuclear applications. The principle source reaction is H-2(d,n)He-3. It produces a nearly mono-energetic group of neutrons. However, a lower-energy continuum neutron spectrum is produced by the H-2(d;n,p)H-2 reaction and also by deuterons which strike various components in the target assembly. The present target is d… more
Date: March 1, 1992
Creator: Feautrier, D. & Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MHD considerations for a self-cooled liquid lithium blanket

Description: The magnetohydrodynamic (MHD) effects can present a feasibility issue for a self-cooled liquid metal blanket of magnetically confined fusion reactors, especially inboard regime of a tokamak. This pressure drop can be significantly reduced by using insulated wall structure. A self-healing insulating coating has been identified, which will reduce the pressure drop by more than a factor of 10. The future research direction to further quantify the performance of this coating is also outlined.
Date: March 1, 1992
Creator: Sze, D. K.; Mattas, R. F.; Hull, A. B.; Picologlou, B. F. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

MHD considerations for a self-cooled liquid lithium blanket

Description: The magnetohydrodynamic (MHD) effects can present a feasibility issue for a self-cooled liquid metal blanket of magnetically confined fusion reactors, especially inboard regime of a tokamak. This pressure drop can be significantly reduced by using insulated wall structure. A self-healing insulating coating has been identified, which will reduce the pressure drop by more than a factor of 10. The future research direction to further quantify the performance of this coating is also outlined.
Date: March 1, 1992
Creator: Sze, D. K.; Mattas, R. F.; Hull, A. B.; Picologlou, B. F. & Smith, D. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

U.S. Contribution 1994 Summary Report Task T12: Compatibility and irradiation testing of vanadium alloys

Description: Vanadium alloys exhibit important advantages as a candidate structural material for fusion first wall/blanket applications. These advantages include fabricability, favorable safety and environmental features, high temperature and high wall load capability, and long lifetime under irradiation. Vanadium alloys with (3-5)% chromium and (3-5)% titanium appear to offer the best combination of properties for first wall/blanket applications. A V-4Cr-4Ti alloy is recommended as the reference compositio… more
Date: March 1, 1995
Creator: Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some guidelines for the evaluation of nuclear data

Description: Modern data evaluation methodology draws upon basic principles from statistics. It differs from earlier ad hoc approaches which are completely subjective (e.g., eye guides to data) or are objective in a limited sense (e.g., combinations of reported data by a simple least-squares procedure without regard to correlations in the data errors or a careful scrutiny of the data included in the evaluation). In addition to utilizing more rigorous mathematical procedures, modern evaluation methodology in… more
Date: March 20, 1996
Creator: Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of metal-clad filled evacuated panel superinsulation

Description: This Cooperative Research and Development Agreement (CRADA) was between Aladdin Industries, Inc. and Lockheed Martin Energy Research Corp. The purpose of the CRADA was to determine the thermal performance of various metal claddings used to encapsulate Filled Evacuated Panel (FEP) superinsulation and to optimize the cost versus thermal performance of the claddings. A FEP superinsulation is a new type of superinsulation with the potential for saving large amounts of energy in buildings, building … more
Date: March 1, 1997
Creator: Wilkes, K. E.; Strizak, J. P.; Weaver, F. J.; Besser, J. E. & Smith, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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