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Books & Journals / Journal of ASTM International (JAI) / Citation Page/

Volume 2, Issue 3 (March 2005)

Online ISSN: 1546-962X
Published Online: 28 February 2005
Page Count: 14

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Use of the Irradiation-Thermal Creep Model of Zr-1% Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods

Rogozyanov, A
State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia

Smirnov, A
State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia

Kanashov, B
State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia

Polenok, V
State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia

Nuzhdov, A
State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia

(Received 16 March 2003; accepted 7 December 2004)
JOURNAL JAI
Abstract
The objective of this work was firstly to categorize the data on dimensional change of the VVER fuel rods and to identify the primary variables influencing performance, and secondly to benchmark the irradiation-thermal creep model for Zr-1 % Nb alloy cladding tubes against the VVER fuel rod dimensional changes data. The creep model was developed using the results of in-pile and out-of-pile tests of tube specimens.

Data arrays on the change of fuel rod diameter and length were obtained during examination of eight VVER-440 fuel assemblies and 16 VVER-1000 fuel assemblies. Qualitative analysis was performed of the measurement results presented as dependencies of averaged axial strain on burnup.

Similar calculated dependencies were obtained using the creep model considering the irradiation growth strain. The quantitative analysis showed that differences between the calculated and actual dimensional changes of the fuel rods did not exceed 3–4.5 % for VVER-440 and 7 % for VVER-1000.

Keywords:
creep model, dimensional change, fuel rod cladding, irradiation growth, irradiation-thermal creep, VVER fuel rods, zirconium, zirconium alloy

Paper ID: JAI12426
DOI: 10.1520/JAI12426

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Author Rogozyanov, A Affiliation State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia Author Smirnov, A Affiliation State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia Author Kanashov, B Affiliation State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia Author Polenok, V Affiliation State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia Author Nuzhdov, A Affiliation State Scientific Center of RF RIAR, Dimitrovgrad, Ulyanovsk region, Russia Title: Use of the Irradiation-Thermal Creep Model of Zr-1% Nb Alloy Cladding Tubes to Describe Dimensional Changes of VVER Fuel Rods Symposium: Zirconium in the Nuclear Industry: Fourteenth International Symposium, 2004-6-15
Committee: B10 on Reactive and Refractory Metals and Alloys