Entity

Time filter

Source Type

Fontenay - sous - Bois, France

The French Institut de radioprotection et de sûreté nucléaire is a public official establishment with an industrial and commercial aspect created by the AFSSE Act and by the February 22, 2002 decreed n°2002-254. The IRSN is placed under the conjoint authority of the Defence minister, the Environmental minister, the Industry minister and the Health and Research minister.The IRSN gathers more than 1 500 experts and researchers from the Institut de protection et de sûreté nucléaire and the Office de protection contre les rayonnements ionisants . These scientists are thus competent on nuclear safety, radioactive protection and control of nuclear and sensitive materials.The IRSN realize investigations, expertise assessements and studies on the fields of nuclear safety, protection against ionizing radiation, protection and control of nuclear material, and protection against voluntary ill-advised acts.IRSN officers are armed with the American made Smith & Wesson M&P9 pistol. Wikipedia.


Beaugelin-Seiller K.,Institute for Radiological Protection and Nuclear Safety
Journal of Environmental Radioactivity | Year: 2016

Within a recent model intercomparison about radiological risk assessment for contaminated wetlands, the influence of soil saturation conditions on external dose rates was evidenced. This issue joined concerns of assessors regarding the choice of the soil moisture value to input in radiological assessment tools such as the ERICA Tool. Does it really influence the assessment results and how? This question was investigated under IAEA's Modelling and Data for Radiological Impacts Assessments (MODARIA) programme via 42 scenarios for which the soil water content varied from 0 (dry soil) to 100% (saturated soil), in combination with other parameters that may influence the values of the external dose conversion coefficients (DCCs) calculated for terrestrial organisms exposed in soil. A set of α, β, and γ emitters was selected in order to cover the range of possible emission energies. The values of their external DCCs varied generally within a factor 1 to 1.5 with the soil water content, excepted for β emitters that appeared more sensitive (DCCs within a factor of about 3). This may be of importance for some specific cases or for upper tiers of radiological assessments, when refinement is required. But for the general purpose of screening assessment of radiological impact on fauna and flora, current approaches regarding the soil water content are relevant. © 2015 Elsevier Ltd. Source


Taveau J.,Institute for Radiological Protection and Nuclear Safety
Journal of Loss Prevention in the Process Industries | Year: 2010

After the disaster of AZF plant in Toulouse on 21 September 2001 (31 people killed, 3000 injured and 3 billion dollars of damage), France adopted a new law relative to safety reports and land-use planning on 30 July 2003. This law asks for the investigation of all representative scenarios and the assessment of their probabilities to demonstrate the acceptable level of safety of an industrial facility. Therefore significant changes were introduced in the way of doing risk analysis in France and some difficulties were found for the implementation of a probabilistic approach.This paper presents the new approach of risk analysis established by the French Ministry of the Environment, and particularly focuses on:. • the benefits and limits of the semi-quantitative probabilistic assessment method;. • the benefits and difficulties to use a quantitative probabilistic assessment method;. • some learning from the risk analysis approaches carried out in the nuclear industry;. • some discussion about the national matrix to appreciate the gravity of human consequences from an accident outside facilities. © 2010 Elsevier Ltd. Source


De Luze O.,Institute for Radiological Protection and Nuclear Safety
Nuclear Engineering and Design | Year: 2013

The paper gives a code-based interpretation of the experimental BECARRE program carried out at the "Institut de Radioprotection et de Sureté Nucléaire" (IRSN) between 2005 and 2010, using the severe accident (SA) code ASTEC/ICARE. As part of the International Source Term Program (ISTP), the BECARRE program focuses on boron carbide (B4C) effects during SA conditions, when B4C is used as an absorber material in French PWRs. Steam oxidation of solid B4C pellets (at 1200-1800 °C), as well as oxidation of molten B4C bearing mixtures up to 9 wt% of B4C dissolution (at 1289-1527 °C) are studied, as well as degradation of 60 cm-long control rod (CR) segments representative of a PWR geometry (up to ∼2000 °C). Temperature and outlet gas releases (steam, H2, CO, CO2) measured in line, and post-test examinations (radiography, tomography, microscopic examinations) give available data to code validation and interpretation. The oxidation rates of the B4C bearing melts have been found always lower than the rates of the solid pellet oxidation in similar conditions, as modeled in ASTEC. For the degradation of the CRs, it is shown that for temperature above 1600 °C, the main effect of the B4C is more toward a mitigation of the hydrogen production rather than increasing it by additional oxidation of boron compounds. No large increases of the hydrogen release after the failure of the guide tube (GT) have been measured, due to downward relocation of the low viscosity B4C bearing melts inside the 60 cm-height CR segments. The ZrO2 oxide layer formed on the outer surface of the GT has been found very protective, leading to failure only above 1650 °C. Both isothermal and runaway thermal conditions have been used to bring about limited GT failure showing that the main mechanisms leading to failure are linked to deformation of the initial geometry, close contacts between materials, and subsequent eutectic material formations. Such a limited degradation for the GT is not modeled in the code. © 2013 Elsevier B.V. Source


Lacoste V.,Institute for Radiological Protection and Nuclear Safety
Radiation Measurements | Year: 2010

The Laboratory for Neutron Metrology and Dosimetry of the Institute for Radiation Protection and Nuclear Safety has undertaken a study related to the optimization of the geometry of a long counter to determine the neutron fluence reference values at the AMANDE facility. This study was performed on the basis of a De Pangher long counter design. The materials, the dimensions and the geometry were varied and the consequences on the response function were studied. Different parameters were optimized to flatten the neutron response energy distribution, over a wide energy range, from a few eV's to a few MeV's. The aim of this paper is to present the results of the study performed by using intensive Monte-Carlo simulations which helped in the design of the new IRSN long counter. © 2010 Published by Elsevier Ltd. All rights reserved. Source


Guipaud O.,Institute for Radiological Protection and Nuclear Safety
Advances in experimental medicine and biology | Year: 2013

All tissues can be damaged by ionizing radiation. Early biomarkers of radiation injury are critical for triage, treatment and follow-up of large numbers of people exposed to ionizing radiation after terrorist attacks or radiological accident, and for prediction of normal tissue toxicity before, during and after a treatment by radiotherapy. The comparative proteomic approach is a promising and powerful tool for the discovery of new radiation biomarkers. In association with multivariate statistics, proteomics enables measurement of the level of hundreds or thousands of proteins at the same time and identifies set of proteins that can discriminate between different groups of individuals. Human serum and plasma are the preferred samples for the study of normal and disease-associated proteins. Extreme complexity, extensive dynamic range, genetic and physiological variations, protein modifications and incompleteness of sampling by two-dimensional electrophoresis and mass spectrometry represent key challenges to reproducible, high-resolution, and high-throughput analyses of serum and plasma proteomes. The future of radiation research will possibly lie in molecular networks that link genome, transcriptome, proteome and metabolome variations to radiation pathophysiology and serve as sensors of radiation disease. This chapter reviews recent advances in proteome analysis of serum and plasma as well as its applications to radiation biology and radiation biomarker discovery for both radiation exposure and radiation tissue toxicity. Source

Discover hidden collaborations