Mieux connaître le devenir biologique des futurs matériaux nucléaires, une nécessité pour maintenir un bon niveau de radioprotection

Métivier, Henri; Guillaumont, R.

doi:10.1051/radiopro:2007008

Cited by 4 publications

(3 citation statements)

References 55 publications

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“…Il pourrait tout naturellement trouver sa place dans de nouveaux programmes de recherche pour préparer les futurs réacteurs. À cet égard d'autres recherches de même type en radiotoxicologie ont été récemment proposées (Métivier et Guillaumont, 2007).…”

Section: Resultsunclassified

Le stockage définitif des déchets radioactifs et la radioprotection

Métivier¹

2008

Radioprotection

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RÉSUMÉPour des raisons d'efficacité opérationnelle, la CIPR a bâti un système dosimétrique s'appuyant sur l'additivité des effets sur la santé quelle que soit la nature du rayonnement et que l'exposition soit d'origine externe ou interne à l'individu exposé. Ce système a rempli son rôle, le bilan de la radioprotection est aujourd'hui jugé bon. Aujourd'hui, le challenge posé à l'énergie nucléaire est de faire la démonstration que la gestion de ses déchets éventuellement stockés en profondeur sera sans danger pour les générations futures. Le scénario envisagé est lié au retour vers la biosphère avec pour conséquence une contamination interne par ingestion de radionucléides à vie longue. ABSTRACT Final storage of radioactive waste and radiological protection. For operational effectiveness, ICRP built a dosimetric system based on the additivity of the effects whatever are the nature of the radiation and the origin of the exposure, external or internal. This system fulfilled the assigned role; the assessment of the protection against radiation is good. Today, the challenge to overcome with regard of the nuclear energy is to make the demonstration that the management of disposed wastes in geological formations will be without risk to the future generations. The scenario considered is related to the return towards the biosphere and an internal contamination by ingestion of long-lived radionuclides. Is the current radiological protection system adapted to this situation? What means irradiation alpha? What does one really know in dosimetric and risk terms for the chronicity of internal exposures? As many questions for which we always do not have the answer and that it is thus necessary to consider at the time when one recommends a dialogue with the stakeholders and that recent scientific observations call into question many certainties. New research programmes in radiotoxicology appear absolutely necessary to answer these legitimate questions. The example of the step of pharmaceutical industry for obtaining the marketing authorizations of the drugs is to be meditated.

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Section: Resultsunclassified

Le stockage définitif des déchets radioactifs et la radioprotection

Métivier¹

2008

Radioprotection

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“…In order to obtain specific absorption values for members of public, it would be useful to extend this study to environmental compounds such as estuarine silt (Morgan et al 1990). Furthermore, specific absorption parameters should be determined in the future for new Pu chemical forms expected to be present in the fourth generation of nuclear reactor but have not yet been experimentally studied in order to design monitoring programmes for workers and to anticipate dose calculation (Métivier and Guillaumont 2007).…”

Section: Discussionmentioning

confidence: 99%

Absorption of plutonium compounds in the respiratory tract

Davesne¹,

Paquet²,

Ansoborlo³

et al. 2010

J. Radiol. Prot.

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In order to optimise the monitoring of potentially exposed workers, it is desirable to determine specific values of absorption for the compounds handled. This study derives specific values of absorption rates for different chemical forms of plutonium from in vitro and animal (monkeys, dogs, mice, rats) experiments, and from human contamination cases. Different published experimental data have been reinterpreted here to derive values for the absorption parameters, f(r), s(r) and s(s), used in the human respiratory tract model currently adopted by the International Commission on Radiological Protection (ICRP). The consequences of the use of these values were investigated by calculating related committed effective doses per unit intake. Average and median estimates were calculated for f(r), s(r), and s(s) for each plutonium compound, that can be used as default values for specific chemical forms instead of the current reference types. Nevertheless, it was shown that the use of the current ICRP reference absorption types provides reasonable approximations. Moreover, this work provides estimates of the variability in pulmonary absorption and, therefore, facilitates analyses of the uncertainties associated with assessments, either from bioassay measurements or from prospective calculations, of intake and dose.

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“…In support of this hypothesis involving plutonium chemical forms with a biokinetic behaviour different from that described in the reference models of the ICRP (absorption types S and M), complementary studies would be necessarynot only on the chemical and granulometric levels but also on the anatomopathological level using animal experiments (Métivier et Guillaumont, 2007).…”

Section: Biokinetic Mechanismsmentioning

confidence: 99%