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A high-fluence fusion neutron source

Description: A conceptual design of a D-T fusion facility for continuous production of 14-MeV neutron wall loading from 5 to 10 MW/m/sup 2/ at the plasma surface is presented. In this design, D-T neutrons are produced in a linear, two-component plasma formed by neutral beam irradiation of a fully ionized warm plasma target. The beam energy, which is deposited in the center, is transferred to the warm plasma mainly by electron drag and is conducted along the target plasma column to end regions where it is ab… more
Date: February 17, 1988
Creator: Coensgen, F. H.; Casper, T. A.; Correll, D. L.; Damm, C. C.; Futch, A. H.; Logan, B. G. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Fiscal year 1977 DT fusion neutron irradiations and dosimetry at the LLL Rotating Target Neutron Source, October 26, 1977

Description: The DT fusion neutron irradiation of 352 samples during 16 irradiation periods (beam-on time of more than 1219 hours) is described. Experiments from 16 individuals representing eight institutions are summarized. Maximum flux in any of the room temperature runs was 9 x 10'' neutrons/cm/sup 2/-sec for an 80 hour irradiation. The number of the UCID dosimetry reports detailing each of the irradiations are given.
Date: May 17, 1978
Creator: MacLean, S.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Description: Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Three Dimensional Flux Control

Description: Recent correlations of slug rupture data have indicated that the failure rate increases markedly with specific slug power. After the fact flux traverses have shown that a large share of the ruptures have occurred in conjunction with flux peaks significantly higher than normally expected. If more complete in-core flux information were available, it is expected that a major portion of the ruptures could be shown as having been caused by abnormally high flux peaks. However, at present.there is nei… more
Date: December 17, 1958
Creator: Owsley, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DT fusion neutron irradiation of LLL Nb/sub 3/Sn and LLL superconductor wires at 4. 2/sup 0/K

Description: The DT fusion neutron irradiation of one LLL superconductor wire and one LLL Nb/sub 3/Sn foil at 4.2/sup 0/K is described. The sample position, beam-on time, and neutron dose record are given. The results from two ''profile'' dosimetry foils measuring the lateral variation in neutron flux are included.
Date: May 17, 1977
Creator: MacLean, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tory II-C reactor cold critical assembly program

Description: Declassified 27 Nov 1973. The cold critical experiments with the Tory II-C reactor were performed in the critical facility of the Lawrence Radiation Laboratory at Livermore. The reactor is described briefly; the experimental equipment and the arrangement for the experiments is described in detail. The core poison was removed without difficulty, and criticality was achieved at 1624 hours July 14, 1965. With the design core configuration the shutdown margin was less than had been intended; critic… more
Date: January 17, 1964
Creator: Morton, J.R. III; Varljen, T.C.; Petruzzi, J. Jr.; Piowaty, J.M. & Gardner, L.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROPOSAL FOR AN ADVANCED ENGINEERING TEST REACTOR-ETR II

Description: The results of a study are presented which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR, or in existing commercial test reactors. To accomplish the design objectives called for, a reactor producing perturbed neutron fluxes exceeding 10/sup 15/ thermal neutrons per square centimeter per second and 1.5 x 10/sup 15/ e… more
Date: March 17, 1960
Creator: deBoisblanc, D R
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Critical Experiments on a Small Reactor of Enriched U-235 with Al-H₂O Moderator and Beryllium Reflector

Description: From introduction: "The purpose of the present report is to describe briefly certain improvements that have been made in the experimental facilities and to present the results of further measurements on critical masses and spatial neutron flax distributions in Be reflected reactors having square and thin slab geometries."
Date: August 17, 1948
Creator: Martin, A. B. & Mann, M. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monitoring Thermal and Resonance Neutron Flux

Description: The monitoring of thermal and resonance neutron flux in a thermal reactor having high flux over periods of time from 1 to 12 months using think Co foils is considered. Special attention is paid to the many correction factors to be applied to the activation data; neutron temperature, effective cadmium cutoff energy, burnout of Co59 and Co60, and decay of Co60. Results on a homogeneity test of 10 mil, 0.08% Co-A1 alloy foils is given.
Date: August 17, 1953
Creator: Heineman, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Damage Calculations for the FUBR and BEATRIX Irradiations of Lithium Compounds in EBR-II and FFTF

Description: The Fusion Breeder Reactor (FUBR) and Breeder Exchange Matrix (BEATRIX) experiments were cooperative efforts by members of the International Energy Agency to investigate the irradiation behavior of solid breeder materials for tritium production to support future fusion reactors. Lithium ceramic materials including Li{sub 2}O, LiAlO{sub 2}, Li{sub 4}SiO{sub 4}, and Li{sub 2}ZrO{sub 3} with varying {sup 6}Li enrichments from 0 to 95% were irradiated in a series of experiments in the Experimental … more
Date: June 17, 1999
Creator: Greenwood, L. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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