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Encapsulated Nuclear Heat Source

The Encapsulated Nuclear Heat Source (ENHS, ANNEX XX) is a modular lead-bismuth cooled reactor of 50-75 MW(e) with a 20-year or even longer refuelling interval. The reference ENHS reactor has two coolant circuits, both being of a pool type the primary coolant circulates inside the ENHS module while the secondary (intermediate) coolant circulates in the pool the ENHS module is inserted in. The reactor design incorporates optimum combinations of reactivity feedbacks and is fissile self-sufficient. [Pg.118]

WADE, D.C., et al., ENHS the encapsulated nuclear heat source - a nuclear energy concept for emerging worldwide energy markets, ICONE-10 (Proc. of 10 Int. Conf on Nuclear Engineering, Arlington VA, US, 2002), ICONE-10-22202, ASME. [Pg.424]

The Encapsulated Nuclear Heat Source (ENHS) concept [XV-9] developed by the University of California at Berkeley (the USA) is a similar design concept. [Pg.440]

ENCAPSULATED NUCLEAR HEAT SOURCE PRELIMINARY REACTOR MODULE LAYOUT REFERENCE CASE NLP 4 (ENHS) STUDY... [Pg.576]

CONWAY, L., et al.. Promising design options for the encapsulated nuclear heat source reactor, ICONE-9 (Proc. 9 Int. Conf on Nuclear Engineering, Nice, France, April 8-12,2001), Paper ICONE9-417, ASME. [Pg.583]

GREENSPAN, E., et al.. The encapsulated nuclear heat source reactor - a generation IV reactor, GLOBAL-2001 (Paper presented at Int. Conf, Paris, France, September 2001), ANSENS. [Pg.583]

XX-12] BUONGIORNO, J., BARAK, A., GREENSPAN, E., Irradiation performance of the metal fuel for the encapsulated nuclear heat source, Trans. American Nuclear Society, 86, 348-349 (Hollywood, FL, June 2002). [Pg.584]

XX-13] HONG, S.G., GREENSPAN, E., KIM, Y.I., Once-for-life core for the encapsulated nuclear heat source (ENHS) reactor, PHYSOR-2002 (Proc. Int. Conf. on the New Frontiers of Nuclear Technology Reactor Physics, Safety and High-Performance Computing, Seoul, Korea, October 7-10, 2002), paper lOB-04 (2002). [Pg.584]

The STAR portfolio of designs was initiated in the 1997 time frame and is comprised of SSTAR, STAR-LM and STAR-H2. They employ technological innovations of increasing lead-time to deployment (see Fig. XXIV-18). The STAR portfolio share many features with the Encapsulated Nuclear Heat Source (ENHS, see ANNEX XIX) and the 4S concepts, see Fig. XXIV-18. The Pb technology and nitride fuel technology are in common with the BREST designs. [Pg.701]

Several advanced nuclear power plant designs with long-life cores already exist for deployment for the long term, requiring a large development effort for fuel and plant technology, e.g. the lead cooled encapsulated nuclear heat source [XIX-1]. [Pg.535]

SNU s first international collaboration project on LPR R D was conducted under I-NERI program for developing the conceptual design of Encapsulated Nuclear Heat Source (ENHS) (Greenspan, 2003). The ENHS design of full natural circulation of LBE was then selected as Gen-IV LFR reference design. The natural circulation concept was further developed at SNU-NUTRECK as a pool-type small modular... [Pg.359]


See other pages where Encapsulated Nuclear Heat Source is mentioned: [Pg.551]    [Pg.551]    [Pg.551]    [Pg.584]    [Pg.584]    [Pg.548]    [Pg.365]   
See also in sourсe #XX -- [ Pg.359 ]




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