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Power reactor, conceptual design

W. M. Stacey, Jr., Tokamak Experimental Power Reactor Conceptual Design, ANL/CTR-76-3, Argonne National Laboratory, Argonne, Illinois (1976). [Pg.489]

Single-fluid Two-region Aqueous Homogeneous Reactor Power Plant— Conceptual Design and Feasibility Study, US. EC Report NPG-171. Commonwealth Edison Company (Nuclear Power Group) and Babcock Wilcox Company, July 1957. [Pg.26]

General Electric Company, Atomic Power Equipment Department, Homogeneous Circulation Fuel Reactor Power Plant Conceptual Design Study Report, US.< EC Report GEAP-2(Del.), May 31, 1955. [Pg.558]

A conceptual design and selection of an ATR biodiesel processor for a vehicle fuel cell auxiliary power unit were reported by Specchia et al. [81]. Three processor options were compared for H2 production with respect to efficiency, complexity, compactness, safety, controllability and emissions. The ATR with both high-temperature shift (HTS) and low-temperature shift (LTS) reactors showed the most promising results. [Pg.299]

Table 1. Comparison of the major characteristics of three conceptual tokamak power reactor designs of the University of Wisconsin... Table 1. Comparison of the major characteristics of three conceptual tokamak power reactor designs of the University of Wisconsin...
Most reliable are the data on neutron fluxes which are determined by the plasma power density, reactor geometry and structural parameters. Most of the conceptual power reactor design studies contain a detailed neutronics analysis giving the energy as well as the spatial distribution of neutron fluxes. [Pg.61]

Badger, B., Conn, R. W., Kulcinski, G. L., et aL UWMAK-II, A Conceptual Tokamak Power Reactor Design. Nucl. Eng. Dept., Univ. of Wisconsin, Report UWFDM-112. Wisconsin, 1975... [Pg.101]

Oka Y, Koshizuka S. (1998) Conceptual design study of advanced power reactors. Pro0 NuclEner 32 163-177. [Pg.274]

Y. Chikazawa et al., Conceptual Design of Hydrogen Production Plant with Thermochemical and Electrolytic Hybrid Method Using a Sodium Cooled Reactor , ICAPP 05-5084, 2005 International Congress on Advances in Nuclear Power Plants, Seoul (May 2005). [Pg.71]

On the basis of commercially produced modules SVBR-75/100 it is expedient to develop the design of modular NPP of large power (1 GW and more at the same unit). The prospect for that principle of designing NPP is shown in conceptual design developed in the USA (PRISM) [24] and in Japan (4S) [25]. However, use of this principle for LBC cooled reactors is the most effective. [Pg.146]

Fig. 3. Conceptual design for the Tokamak Experimental Power Reactor (Oak Ridge National... Fig. 3. Conceptual design for the Tokamak Experimental Power Reactor (Oak Ridge National...
Table III. Conceptual Designs for a Tokamak Experimental Power Reactor ... Table III. Conceptual Designs for a Tokamak Experimental Power Reactor ...
L. Guimaraes et. alii, Conceptual Design of an Intermediate Heat Exchanger for a 60 MWt Experimental Fast Reactor , Proceedings of the 9th Power Plant Dynamics, Control Testing Symposium, May 24-26, Knoxville, Tennessee, USA (1995). [Pg.12]

JAPC conducted for the past several years conceptual design studies of the DFBR-1 in accordance with the basic policy of the Federation of Electric Power Companies (FEPC) and confirmed the feasibility of top entry loop type reactor. [Pg.118]

As for the demonstration fast breeder reactor (DFBR) of Japan, the Japan Atonaic Power Company (JAPC) conducted conceptual design studies for the past several years, and confirmed the feasibility of top entry loop type reactor concept. Based on results of the design studies, the Federation of Electric Power Companies (FEPC) decided in January 1994 to start construction of the DFBR plant at the beginning of the 2000 s. FEPC also decided the basic specifications of the DFBR plant. [Pg.141]

In the future, electricity production at large NPPs is likely to remain the main application of nuclear energy. This factor and the reduction of unit costs with increase in the power and number of nuclear units were the reasons for conceptual study of a 1,200 MWe lead-cooled fast reactor as a candidate basic component of a large-scale nuclear power mix. The BREST-OD-300 being developed as a prototype of the BREST-1200 reactor, their design and engineering features are largely similar, as may be seen from the data of Table 58.6 (ISTC 2001 Adamov et al. 1997). [Pg.2717]

Ponomarev-Stepnoi NN, Usov VA (1995) Conceptual design of the bimodal nudear power system based on the Romashka type reactor the thermionic energy conversion system. In 12th Symposium on... [Pg.2757]

Today the conceptual design of the reactor plant, turbine plant, automated process control system and main principles for the nuclear power station are already completed. [Pg.389]

On the basis of the conceptual design of the reactor plant and the main principles of the nuclear power station project the first version of the preliminary safety report has been developed and presented to the Russian regulatory organizations for approval. [Pg.389]

G. A. Carlson, K. R. Schultz, A. C. Smith, Jr., "Definition and Conceptual Design of a Small Fusion Reactor," Electric Power Research Institute Report ER-1045 (1979). [Pg.92]

Based on the parameters given in Table 1 a conceptual design[31] was prepared in 1978 as part of a study of alternate reactor concepts sponsored by the Electric Power Research Institute the results of this study are reported in a paper by Dr. Krall at this meeting. Engineers from the Bechtel Corporation worked with the proponents of each concept to arrive at a conceptual design of a lOOOMW(e) power plant based on that approach. The Linus reactor that emerged from this study is shown in Figure 11. [Pg.273]

L. Kelly et al., "Status Report on the Conceptual Design of a Commercial Tokamak Hybrid Reactor (CTHR)," Westinghouse Fusion Power Systems Department Report WFPS-TME-79-022 (1979). [Pg.416]

The conceptual design of the advanced reactor plant BN-1600 was completed in 1992, in full compliance with the up-to-date requirements for safety and economic efficiency of the new generation NPPs. It is expected that this design can be realized in Russian Federation not earlier than 2020, taking into account the fact that in the near future the fast reactor development programme in this country will be primarily focused on construction of the pilot BN-800 reactors, and creation of the closed nuclear fuel cycle production plants. This phase is of exceptional importance for the subsequent development of fast reactors and should precede their wide incorporation into the nuclear power park. [Pg.425]


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See also in sourсe #XX -- [ Pg.681 ]




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