Erfahrungs- und Forschungsbericht 2012 - Ensi

Erfahrungs- und Forschungsbericht 2012 - Ensi

tent reduces. The dissolution is intensified in the


However, a more detailed study indicates that in

the metal side of the interface:

a- The βNb-type precipitates dissolve at a slower

rate, or knowing that their composition is much

richer in Nb, the time needed for final dissolution

is much longer.

b- Regarding the amorphization under irradiation,

the βNb-type and the Cr containing precipitates

do not amorphize, in the metal part of the interface.

This is not the case of the Fe containing precipitates,

which amorphize already in the metal. In

the oxide side of the interface, βNb-type and the

Cr containing precipitates show a delayed oxidation

in the vicinity of interface and only oxidize

when at a distance from the metal-oxide interface.

This is not the case of Fe containing precipitates. It

is worth noting that once oxidized, all precipitates

are amorphized.

National Cooperation

The Service of Microscopy and Nanoscopy (SMN)

of the «Centre Suisse d’Electronique et Microtechnique»

(CSEM) has provided access, for the use

of TEM.

International Cooperation

This project has been started in collaboration with

the OECD Halden reactor project, and the IFE

Kjeller laboratory.

Assessment 2012

As mentioned in the previous part, the examination

of the present irradiated cladding segments

should be considered as a great success, since

access to such cladding materials from the reactor

and the preparation of such materials for TEM

studies needs a great amount of effort. The results

will be published in collaboration with the

OECD-HRP and the fuel suppliers. With the 2012

results, the examination of the samples selected

for the TEM studies in the framework of this project

can be considered as completed. The studies

can clearly explain the role of Nb on the resistance

to dissolution of precipitates under irradiation in all

materials studied.


The authors wish to thank the OECD Halden reactor

projector team, T.M. Karlsen, and B. Oberländer

and M. Espeland and H. Jenssen from IFE Kjeller,

for their collaboration and their support of the

project, the supply of the cladding rings and the

fruitful meetings and discussions during the last

years. A. Lagotzki from PSI is acknowledged for his

support during the transport phase of this project.

A. Bullemer and J. Krbanjevic are thanked for the

assistance with optical and FIB sample preparation.


1. M. Nakata and E. Hauso, Summary of characterisation

data on cladding materials used in

the corrosion test IFA-638 and in the creep test

IFA-617, 1998, OECD Halden Reactor Project

HWR-566, p. 19; and P. Bennett, R. Stoenescu

and T. Karlsen, The PWR corrosion and hydriding

test IFA-638. Final report, HWR-840,


2. S. Abolhassani, G. Bart and A. Jakob, Examination

of the chemical composition of irradi-ated

zirconium based fuel claddings at the metal/

oxide interface by TEM. Journal of Nuclear Materials

399, 2010 (1), p. 1–12.

3. C. Proff and S. Abolhassani, IFA-638-TEM Examinations

of Metal-oxide interface of Zirconium

alloys, ENSI Research Report, 2011.

4. S. Doriot, D. Gilbon, J.L. Bechade, M.H. Mathon,

L. Legras and J.P. Mardon, Microstruc-tural stability

of M5 (TM) alloy irradiated up to high neutron

fluences. ASTM STP 1467, 2005, p. 175-201.

5. V.N. Shishov, M.M. Peregud, A.V. Nikulina, P.V.

Shebaldov, A.V. Tselischev, A.E. Novoselov, G.P.

Kobylyansky, Z.E. Ostrovsky and V.K. Shamardin,

Influence of zirconium alloy chemical

composition on microstructure formation and

irradiation induced growth. ASTM STP 1423,

2002, p. 758–778.

6. G.P. Sabol, R.J. Comstock, R.A. Weiner, P.

Larouere and R.N. Stanutz, In-Reactor Corrosion

Performance of ZIRLO and Zircaloy-4.

ASTM STP 1245, 1994, p. 724–744.

7. S. Abolhassani, Minutes of the meeting in IFE,

Kjeller for the selection of IFA-638 samples for

TEM analysis, 2009, PSI report AN-46-09-08,

p. 8.

8. S. Abolhassani, P. Gasser; «Preparation of TEM

samples of metal-oxide interface by the fo-

ENSI Erfahrungs- und Forschungsbericht 2012 121

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