An Advanced Nuclear Reactor concept is presented which extends Boiling Water Reactor technology with micro-fuel elements (MFE) and produces superheated steam. A nuclear plant with MFE is highly efficient and safe, due to ceramic-clad nuclear fuel. Water is used as both moderator and coolant. The fuel consists of spheres of about 1.5 mm diameter of UO2 with several external coatings of different carbonaceous materials. The outer coating of the particles is SiC, manufactured with chemical vapor disposition (CVD) technology. Endurance of the integrity of the SiC coating in water, air and steam has been demonstrated experimentally in Germany, Russia and Japan. This paper describes a result of a preliminary design and analysis of 3750 MWt (1500 MWe) plant with standard pressure of 16 MPa, which is widely achieved in the vessel of pressurized-water type reactors. The superheated steam outlet temperature of 550 °C elevates the steam cycle to high thermal efficiency of 42%.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3596-0
PROCEEDINGS PAPER
Pebble Bed Boiling Water Reactor Concept With Superheated Steam
G. Tsiklauri,
G. Tsiklauri
Pacific Northwest National Laboratory, Richland, WA
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D. Newman,
D. Newman
Pacific Northwest National Laboratory, Richland, WA
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G. Meriwether,
G. Meriwether
Pacific Northwest National Laboratory, Richland, WA
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V. Korolev
V. Korolev
Pacific Northwest National Laboratory, Richland, WA
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G. Tsiklauri
Pacific Northwest National Laboratory, Richland, WA
D. Newman
Pacific Northwest National Laboratory, Richland, WA
G. Meriwether
Pacific Northwest National Laboratory, Richland, WA
V. Korolev
Pacific Northwest National Laboratory, Richland, WA
Paper No:
ICONE10-22045, pp. 475-481; 7 pages
Published Online:
March 4, 2009
Citation
Tsiklauri, G, Newman, D, Meriwether, G, & Korolev, V. "Pebble Bed Boiling Water Reactor Concept With Superheated Steam." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 14–18, 2002. pp. 475-481. ASME. https://doi.org/10.1115/ICONE10-22045
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