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NEA-1629 IFPE/IFA-508 & 515.

IFPE/IFA-508 & 515, PCMI Behaviour of Thin Cladding Rods, JAERI and HRP

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1. NAME OF EXPERIMENT:  IFPE/IFA-508 and IFPE/IFA-515.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
IFPE/IFA-508 & 515 NEA-1629/01 Arrived 26-JAN-2007

Machines used:

Package ID Orig. computer Test computer
NEA-1629/01 Many Computers
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3. DESCRIPTION

To measure the integrated response of UO2 and its cladding to conditions associated with PCI, the Japan Atomic Energy Research Institute carried out a series of experiments in the Halden BWR. The experiment involved two major objectives. The first was to study the influence of rod design parameters on PCI. Diametral gap, wall cladding thickness, SiO2 additive, and pellet grain size were used as design parameters. The second objective was to study the influence of preirradiation (i.e. burnup) on PCI. The maximum burnup attained in the experiment was 23 MWd/kgU. These research results can be applied to current BWR-type fuel rods.
  
The tests were performed between April 1977 and March 1981.
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9. STATUS
Package ID Status date Status
NEA-1629/01 26-JAN-2007 Arrived at NEADB
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10. REFERENCES
NEA-1629/01, included references:
- Data sheet for IFA-508.1
- Data sheet for IFA-515
- M. Uchida and M. Ichikawa:
In-pile Diameter Measurement of Light Water Reactor test Fuel Rods for
Assessment of Pellet-Cladding Mechanical Interaction
Reprint from Nuclear Technology, Vol.51 pp.33-44 (November 1980)
- K. Yanagisawa:
An Evaluation of the Influence of Fuel Design Parameters and Burnup on
Pellet/Cladding Interaction for Boiling Water Reactor Fuel Rod through in-core
Diameter Measurement
Reprint from Nuclear Technology, Vol.73 pp.361-377 (June 1986)
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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15. NAME AND ESTABLISHMENT OF AUTHORS: JAEA
Tokai-mura, Naka-gun
Ibaraki-ken, 319-11
Japan
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16. MATERIAL AVAILABLE
NEA-1629/01
Data sheet for IFA-508.1
Data sheet for IFA-515
Reprint from Nuclear Technology Vol.51 pp.33-44
Reprint from Nuclear Technology Vol.73 pp.361-377
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: boiling water reactor, pellet clad interaction (pci).