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Fuel channel development for advanced BWR fuel

  • 1. Siemens Power Corporation - Nuclear Division, Richland, WA (United States)
  • 2. Siemens AG KWU/BT51, Erlangen (Germany)

Description

Fuel channels in boiling water reactors direct the coolant flow through the fuel assemblies and provide structural stability during reactor operation. The disadvantages associated with fuel channels are the reduction of flow area available for the fuel bundle and the parasitic capture of neutrons by the wall material. These disadvantages are most significant in BWR/6's because they currently incorporate the thickest fuel channels in the industry (3 mm) and the smallest flow area. This paper presents an advanced fuel channel design developed by Siemens that increases the inside width in BWR/6 fuel channels from 132.5 mm to the standard size of 134.0 mm in BWR/3,4,5 and reduces the amount of wall material by approximately 28%. The larger in-channel flow area improves stability by reducing two phase pressure losses and reduces fuel cycle costs through increased thermal hydraulic performance or by adding more uranium in the fuel. A variant of this design can be used in D-lattice plants in order to improve fuel cycle cost by partial water gap symmetrization. The fuel channel cross section is characterized by thin side walls and thick corners. The thin side walls ensure free movement of the control rod, while the thick corners, where highest stress occurs, minimize bulging on the side walls. Fuel channel bow is controlled by the use of four longitudinal weld seams instead of two. The addition of a wide β-structure to the center of each fuel channel face is expected to reduce bowing. The following section describes the design methodology including stress analysis, creep calculation, and a statistical evaluation of control rod to fuel channel interaction. A brief overview of the manufacturing process is also presented. (author)

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Part of:
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1

Additional details

Publishing Information

Imprint Title
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1
Imprint Pagination
772 p.
Journal Page Range
p. 15A1-15A4
Report number
INIS-XA-N--080

Conference

Title
4. international topical meeting on nuclear thermal hydraulics, operations and safety
Dates
5-8 Apr 1994
Place
Taipei, Taiwan (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35095523
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BOWING; BWR TYPE REACTORS; CONTROL ELEMENTS; FUEL CHANNELS; FUEL CYCLE; FUEL ELEMENT CLUSTERS; STRESSES
Descriptors DEC
DEFORMATION; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref., 5 figs