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U.S. technical report for the ITER blanket/shield: A. blanket: Topical report, July 1990--November 1990

Description: Three solid-breeder water-cooled blanket concepts have been developed for ITER based on a multilayer configuration. The primary difference among the concepts is in the fabricated form of breeder and multiplier. All the concepts have beryllium for neutron multiplication and solid-breeder temperature control. The blanket design does not use helium gaps or insulator material to control the solid breeder temperature. Lithium oxide (Li{sub 2}O) and lithium zirconate (Li{sub 2}ZrO{sub 3}) are the pri… more
Date: January 1, 1995
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of a Magnetic Field on Heat Transfer in a Slotted Channel

Description: The results of numerical and experimental studies of liquid metal heat transfer in slotted channels in a transverse magnetic field are presented. Test results showed an improvement in heat transfer in a straight channel at low and moderate interaction parameter, N. The Nusselt number at small N (around 120) was up to 2 times higher than in turbulent flow without a magnetic field, Peclet number being equal. This effect of heat transfer enhancement is caused by the generation and development of l… more
Date: July 1, 1994
Creator: Evtushenko, I. A.; Kirillov, I. R.; Sidorenkov, S. S.; Hua, T. Q. & Reed, C. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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BEATRIX-II: In-situ tritium recovery data correction

Description: BEATRIX-II was an in-situ tritium recovery experiment in a fast reactor to characterize the irradiation behavior of fusion ceramic breeder materials. Correcting and compiling the in-situ tritium recovery data involved correcting the ion chamber response for the effect of sweep gas composition or amount of hydrogen in the helium sweep gas and for the buildup of background. The effect of sweep gas composition was addressed in the previous workshop. During the operation of Phase I of the experimen… more
Date: September 1, 1993
Creator: Slagle, O. D.; Hollenberg, G. W.; Kurasawa, T. & Verrall, R. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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MHD pressure drops and thermal hydraulic analysis for the ITER breeding blanket design

Description: The breeding blanket design of the International Thermonuclear Experimental Reactor (ITER) is a self-cooled liquid lithium system with a vanadium structure. Electrical insulation of the coolant channel surfaces from the liquid metal is required to reduce the magnetohydrodynamic (MHD) pressure to less than 1 MPa. Insulation is provided by AIN coating at the channel surfaces in contact with lithium. MHD pressure drop and thermal hydraulic analysis of the blanket design is carried out subject to p… more
Date: June 1, 1994
Creator: Hua, Thanh Q. & Gohar, Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design windows for a He cooled fusion reactor

Description: A design window concept is developed for a He-cooled fusion reactor blanket and divertor design. This concept allows study of a parameter regime under which a possible design exists with different design requirements, such as allowable pumping fraction. The concept identifies not only the required parameter regime, but also investigates the robustness of the design, i.e., the validity of the design with change of design parameters and requirements. Some recent directions of helium cooled design… more
Date: October 1, 1993
Creator: Sze, Dai-Kai & Hassanein, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Cryogenic adsorption of low-concentration hydrogen on charcoal, 5A molecular sieve, sodalite, ZSM-5 and Wessalith DAY

Description: The separation of low-concentration hydrogen isotopes from helium is a processing step that is required for ceramic lithium breeding blanket processing. Cryogenic adsorption is one method of effecting this separation. In this study live adsorbents were considered for this purpose: charcoal, 5A molecular sieve, UOP S-115, ZSM-5 and Wessalith DAY. The first two adsorbents exhibit good equilibrium loadings and are shown to be quite effective at adsorbing low-concentration hydrogen isotopes. The la… more
Date: December 1, 1993
Creator: Willms, R. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Present understanding of MHD and heat transfer phenomena for liquid metal blankets

Description: A review of experimental work on magnetohydrodynamic (MHD) and heat transfer (HT) characteristics of liquid metal flows in fusion relevant conditions is presented. Experimental data on MHD flow pressure drop in straight channels of round and rectangular cross-section with electroconducting walls in a transverse magnetic field show good agreement with theoretical predictions, and simple engineering formulas are confirmed. Less data are available on velocity distribution and HT characteristics, a… more
Date: July 1, 1994
Creator: Kirillov, I. R.; Barleon, L.; Reed, C. B. & Miyazaki, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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An assessment of the base blanket for ITER

Description: Ideally, the ITER base blanket would provide the necessary tritium for the reactor to be self-sufficient during operation, while having minimal impact on the overall reactor cost, reliability and safety. A solid breeder blanket has been developed in CDA phase in an attempt to achieve such objectives. The reference solid breeder base blanket configurations at the end of the CDA phase has many attractive features such as a tritium breeding ratio (TBR) of 0.8--0.9 and a reasonably low tritium inve… more
Date: December 31, 1991
Creator: Raffray, A. R.; Abdou, M. A. & Ying, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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In situ tritium recovery from Li{sub 2}O irradiated in fast neutron flux: BEATRIX-II effect of gas composition

Description: The BEATRIX-II irradiation experiment is an in-situ tritium recovery experiment to evaluate the tritium release characteristics of Li{sub 2}O and to characterize its stability under fast neutron irradiation to extended burnups. This is an IEA sponsored experiment which is being carried out in the Materials Open Test Assembly of FFTF. The participants are Japan, Canada and the US. The in-situ tritium recovery experiment includes two specimens: a thin annular specimen capable of temperature chang… more
Date: November 1, 1991
Creator: Slagle, O. D. & Kurasawa, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tritium transport and release from lithium ceramic breeder materials

Description: In an operating fusion reactor,, the tritium breeding blanket will reach a condition in which the tritium release rate equals the production rate. The tritium release rate must be fast enough that the tritium inventory in the blanket does not become excessive. Slow tritium release will result in a large tritium inventory, which is unacceptable from both economic and safety viewpoints As a consequence, considerable effort has been devoted to understanding the tritium release mechanism from ceram… more
Date: May 1, 1994
Creator: Johnson, C. E.; Kopasz, J. P. & Tam, S. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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ANL ITER high-heat-flux blanket-module heat transfer experiments. Fusion Power Program

Description: An Argonne National Laboratory facility for conducting tests on multilayered slab models of fusion blanket designs is being developed; some of its features are described. This facility will allow testing under prototypic high heat fluxes, high temperatures, thermal gradients, and variable mechanical loadings in a helium gas environment. Steady and transient heat flux tests are possible. Electrical heating by a two-sided, thin stainless steel (SS) plate electrical resistance heater and SS water-… more
Date: February 1, 1992
Creator: Kasza, K. E.
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

Fusion neutronics experiments and analysis. Progress report, November 1, 1991--October 31, 1992

Description: UCLA has led the neutronics R&D effort in the US for the past several years through the well-established USDOE/JAERI Collaborative Program on Fusion Neutronics. Significant contributions have been made in providing solid bases for advancing the neutronics testing capabilities in fusion reactors. This resulted from the hands-on experience gained from conducting several fusion integral experiments to quantify the prediction uncertainties of key blanket design parameters such as tritium production… more
Date: December 1, 1992
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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