Published January 1980 | Version v1
Report Open

PCI analysis of a stainless-steel cladding fuel rod for a small-sized PWR under power ramping conditions

  • 1. Japan Nuclear Ship Development Agency, Tokyo
  • 2. Mitsubishi Atomic Power Industries, Inc., Omiya, Saitama, Japan

Description

In order to evaluate the behaviours of a fuel rod for a small sized PWR, PCI analysis has been carried out, with special emphasis on the performances for a rapid power ramping that is important for this type of reactor. The analytical procedures used were divided into two phases. First, the whole-rod-wise calculation was performed by using a general fuel performance code, and the fundamental behaviours of rod were obtained for an averaged operational history over the life of rod. Then, these results were transfered to the second phase analysis, in which very localized PCI behaviours were calculated by using a finite element program. One radial slice was taken out of the axial position of rod where the severest PCI was expected to occur, and it was analyzed in detail for a rapid power ramping condition, taking special consideration for the pellet relocation effect. On the choice of the other calculational conditions, the worst combination of parameters was assumed. It was found, from the results of analysis, that in spite of the conservative calculational conditions, the stresses in clad were well below the clad strength criteria, and excellent performance for power ramping is expected. (author)

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Additional details

Publishing Information

Imprint Title
Specialists' meeting on power ramping and power cycling of water reactor fuel and its significance to fuel behaviour, Arles, France, 14-18 May 1979
Journal Page Range
p. 36-41.
Report number
IWGFPT--5

Conference

Title
Specialists' meeting on power ramping and power cycling of water reactor fuel and its significance to fuel behaviour.
Dates
14 - 18 May 1979.
Place
Arles, France.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
12632893
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; PERFORMANCE; PWR TYPE REACTORS; STAINLESS STEELS; STRESSES
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; FUEL ELEMENTS; IRON ALLOYS; IRON BASE ALLOYS; REACTOR COMPONENTS; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS