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Radiological protection in ITER

Published online by Cambridge University Press:  13 December 2007

H. Maubert ,
T. Pinna ,
M.-T. Porfiri  and
S. Ciattaglia
H. Maubert
Affiliation:
ITER Organisation, Cadarache Joint Work site, 13108 Saint-Paul-lez-Durance, France.
T. Pinna
Affiliation:
ENEA FUS/TEC, Via Enrico Fermi 45, 00044, Frascati, Rome, Italy.
M.-T. Porfiri
Affiliation:
ENEA FUS/TEC, Via Enrico Fermi 45, 00044, Frascati, Rome, Italy.
S. Ciattaglia
Affiliation:
ITER Organisation, Cadarache Joint Work site, 13108 Saint-Paul-lez-Durance, France.
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Abstract

ITER will be the first fusion reactor producing much more energy than that necessary to establish and heat the plasma. This nuclear energy is mainly exported from the plasma by neutrons and deposited in the plasma facing components, generating nuclear activation. One of the elements used in the fusion reaction is tritium, a radioactive isotope of hydrogen. Although some feedback may be used from in service fusion machines, such as JET in England, the ITER radiological protection issues need to be assessed as early as possible. The protection against radiological hazards is, as usual shielding, waiting for radioactive decay, limitation of airborne contaminants, reduction of exposure time, etc. This has been done in the present design and has followed a first step of ALARA studies. Radiation fields have been calculated and work effort estimated leading to the evaluation of a collective yearly dose of 356 p mSv, below the project dose target which is 500 p mSv. A second step of occupational radiological exposure studies should allow refining further the dose estimate as well as the ALARA optimization.

Keywords

nuclear fusionactivationtritiumALARAradiological protection
Type
Research Article
Information
Radioprotection , Volume 42 , Issue 4 , October 2007 , pp. 519 - 534
Copyright
© EDP Sciences, 2007

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References

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