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Thermal-hydraulic stability tests for newly designed BWR rod bundle (step-III fuel type B)

  • 1. Nuclear Fuel Industries, Ltd., Minato-ku, Tokyo (Japan)
  • 2. Tokyo Electric Power Company, Chiyoda-ku, Tokyo (Japan)

Description

The Step-III Fuel Type B is a new fuel design for high burn-up operation in BWRs in Japan. The fuel design uses a 9x9 - 9 rod bundle to accommodate the high fuel duty of high burn-up operation and a square water-channel to provide enhanced neutron moderation. The objective of this study is to confirm the thermal-hydraulic stability performance of the new fuel design by tests which simulate the parallel channel configuration of the BWR core. The stability testing was performed at the NFI test loop. The test bundle geometry used for the stability test is a 3x3 heater rod bundle which has about 1/8 of the cross section area of the full size 9x9 - 9 rod bundle. Full size heater rods were used to simulate the fuel rods. For parallel channel simulation, a bypass channel with a 6x6 - 8 heater rod bundle was connected in parallel with the 3x3 rod bundle test channel. The stability test results showed typical flow oscillation features which have been described as density wave oscillations. The stationary limit cycle oscillation extended flow amplitudes to several tens of a percent of the nominal value, during which periodic dry-out and re-wetting were observed. The test results were used for verification of a stability analysis code, which demonstrated that the stability performance of the new fuel design has been conservatively predicted. (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. 14E1-14E5
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
35095522
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; DRYOUT; FUEL ASSEMBLIES; FUEL RODS; REWETTING; STABILITY; THERMAL HYDRAULICS; THERMODYNAMIC PROPERTIES; TWO-PHASE FLOW
Descriptors DEC
ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 13 figs, 1 tab