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The Advanced Neutron Source

Description: The Advanced Neutron Source (ANS) is a new user experimental facility planned to be operational at Oak Ridge in the late 1990's. The centerpiece of the ANS will be a steady-state research reactor of unprecedented thermal neutron flux ({phi}{sub th} {approx} 9{center dot}10{sup 19} m{sup -2}{center dot}s{sup -1}) accompanied by extensive and comprehensive equipment and facilities for neutron-based research. 5 refs., 5 figs.
Date: January 1, 1989
Creator: Hayter, J. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, August 1961

Description: Progress is reviewed on the following reactors: EBWR; Borax-V; ZPR-III- ZPR-VI; ZPR-IX; EBR-I; and EBR-II. An outline of fast and slow reactor safety studies in TREAT is presented. Progress is also reported in applied nuclear and reactor physics; development of reactor fuels, materials, and components; heat engineering technology; separation processes; and advanced reactor concepts. (T.F.H.)
Date: September 15, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report (for) July 1961

Description: A summary is presented of activities in reactor and general engineering research programs. Discussions are included for developments in EBWR, BORAX-V, ZPR-III. ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Reactor safety studies were performed for fast and thermal reactors. Nuclear technology developments are discussed for applied nuclear and reactor physics, reactor fuels and materials development, heat engineering studies, separations processes, and advanced reactor concepts. (B.O.G.)
Date: August 15, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Boron thermal/epithermal neutron capture therapy

Description: The development of various particle beams for radiotherapy represents an attempt to improve dose distribution, and to provide high LET radiations which are less sensitive to ambient physical and radiobiological factors such as oxygen tension, cell cycle, and dose rate. In general, a compromise is necessary as effective RBE is reduced in order to spread the dose distribution over the anticipated tumor volume. The approach of delivering stable non-toxic isotopes to tumor, and then activating thes… more
Date: January 1, 1982
Creator: Fairchild, R.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, October 1-December 31, 1961

Description: Continued effort is reported on preparation and characterization of PuO/ sub 2/ and UO/sub 2/-- PuO/sub 2/ mixtures. Sintering and characterization of pellets for irradiation tests was emphasized, and efforts were also devoted to plasma torch production of spherical PuO /sub 2/ and coating of oxide materials. PuO/sub 2/ produced by the oxalate process from low concentration feed contains agglomerates which are not readily broken down, while that produced from normal feed contains larger agglome… more
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report for Period January 1 through March 31, 1962

Description: During this reporting period, particular effort was of aced on powder blending and pellet sintering studies prior to irradiation sample fabrication, and, subsequently, the production and characterization of the pellets slated for irradiation. Also, PuO/sub 2/ and UO/sub 2/-PuO/sub 2/ characterization studies were continued, and new techniques are being developed. Specifically, dynamic moisture pickup determinations on PuO/sub 2/ were made in moist air, N, and CO/ sub 2/ atmospheres using a reco… more
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Summary of Shielding Constants for Concrete

Description: The present knowledge of the shielding constants of concrete is summarized. The densities, elemental compositions, and mixes, where available, are given for a wide range of concretes. From these data, various constants useful for shielding calculations were computed. These constants include the removal cross sections, total cross sections, average thermal neutron absorption cross sections, thermal neutron diffusion coefficients, reciprocal thermal neutron diffusion lengths, total gamma-ray line… more
Date: November 1, 1961
Creator: Walker, R.L. & Grotenhuis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR

Description: Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor. Dose rates and fluxes were found to be extremely low. A comparison was made by means of threshold foil techniques between the fast-neutron flux in a beam hole of the reactor during steady-state operation at 1 kw and during a nominal 250 Mw, 30 msec pulse produced by rapid insertion … more
Date: April 23, 1962
Creator: Blosser, T.V.; Freestone, R.M. Jr. & Miller, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Method of Determining the Intermediate Energy Neutron Dose

Description: The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediat… more
Date: March 10, 1961
Creator: Hankins, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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VOID COEFFICIENT OF REACTIVITY ASSOCIATED WITH THE ISLAND REGION OF THE HFIR

Description: Changes in neutron multiplication caused by voids in the island of the HFlR were calculated and measured experimentally. The results indicated that with only water initially in the island the maximum change in neutron multiplication ( DELTA k/sub max) associated with island voids is 0.032 with a corresponding void fraction of 70%. With a simulated 300 g Pu target in the island DELTA k/sub max/ was 0.0l6, and the corresponding void fraction was 42%. In view of these large changes in neutron mult… more
Date: November 15, 1961
Creator: Cheverton, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16

Description: BS>Two-group, two-region criticality calculations were made for 10 and 11 ft diameter tanks. The 10 ft tank required a core radius of 102 cm and the 11 ft tank a core radius of 95 cm for criticality. In the calculations, the fluxes were assumed to go to zero at the edge oi the graphite reflector. The fast group of the two-group calculation was broken down into 3 fast groups. The leakage out of the core and reflector for the 4 energy groups is given. (M.C.G.)
Date: January 29, 1954
Creator: Balent, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-sensitivity transuranic waste assay by simultaneous proton and thermal-neutron interrogation using an electron linear accelerator

Description: Simultaneous photon and neutron interrogation from electron linear accelerator pulses is used as the basis for a unique assay technique for transuranics. Both prompt and delayed neutrons from the induced fissions are counted on a single detection system, and the contributions from each interrogating flux are resolved. Detection limits (3 sigma) for /sup 239/Pu were estimated to be 3 mg for prompt fission neutrons and 6 mg for delayed neutrons. The technique also provides a clear distinction bet… more
Date: January 1, 1982
Creator: Franks, L. A.; Pigg, J. L.; Caldwell, J. T.; Cates, M. R.; Kunz, W. E. & Noel, B. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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