Source:http://linkedlifedata.com/resource/pubmed/id/15353692
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| Predicate | Object |
|---|---|
| rdf:type | |
| lifeskim:mentions | |
| pubmed:issue |
1-4
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| pubmed:dateCreated |
2004-9-8
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| pubmed:abstractText |
The present paper summarises the activity carried out at the ENEA Radiation Protection Institute for updating the methodologies employed for the evaluation of the neutron and photon dose to the exposed workers in case of a criticality accident, in the framework of the 'International Intercomparison of Criticality Accident Dosimetry Systems' (Silène reactor, IRSN-CEA-Valduc June 2002). The evaluation of the neutron spectra and the neutron dosimetric quantities relies on activation detectors and on unfolding algorithms. Thermoluminescent detectors are employed for the gamma dose measurement. The work is aimed at accurately characterising the measurement system and, at the same time, testing the algorithms. Useful spectral information were included, based on Monte Carlo simulations, to take into account the potential accident scenarios of practical interest. All along this exercise intercomparison a particular attention was devoted to the 'traceability' of all the experimental and computational parameters and therefore, aimed at an easy treatment by the user.
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| pubmed:language |
eng
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| pubmed:journal | |
| pubmed:citationSubset |
IM
|
| pubmed:status |
MEDLINE
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| pubmed:issn |
0144-8420
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| pubmed:author | |
| pubmed:issnType |
Print
|
| pubmed:volume |
110
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| pubmed:owner |
NLM
|
| pubmed:authorsComplete |
Y
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| pubmed:pagination |
465-9
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| pubmed:dateRevised |
2008-11-21
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| pubmed:meshHeading |
pubmed-meshheading:15353692-Algorithms,
pubmed-meshheading:15353692-Equipment Failure Analysis,
pubmed-meshheading:15353692-European Union,
pubmed-meshheading:15353692-Gamma Rays,
pubmed-meshheading:15353692-Humans,
pubmed-meshheading:15353692-Italy,
pubmed-meshheading:15353692-Miniaturization,
pubmed-meshheading:15353692-Neutrons,
pubmed-meshheading:15353692-Nuclear Reactors,
pubmed-meshheading:15353692-Occupational Exposure,
pubmed-meshheading:15353692-Photons,
pubmed-meshheading:15353692-Quality Assurance, Health Care,
pubmed-meshheading:15353692-Radiation Dosage,
pubmed-meshheading:15353692-Radiation Protection,
pubmed-meshheading:15353692-Radioactive Hazard Release,
pubmed-meshheading:15353692-Radiometry,
pubmed-meshheading:15353692-Reference Standards,
pubmed-meshheading:15353692-Relative Biological Effectiveness,
pubmed-meshheading:15353692-Reproducibility of Results,
pubmed-meshheading:15353692-Risk Assessment,
pubmed-meshheading:15353692-Risk Factors,
pubmed-meshheading:15353692-Safety Management,
pubmed-meshheading:15353692-Sensitivity and Specificity,
pubmed-meshheading:15353692-Spectrum Analysis
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| pubmed:year |
2004
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| pubmed:articleTitle |
The ENEA criticality accident dosimetry system: a contribution to the 2002 international intercomparison at the SILENE reactor.
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| pubmed:affiliation |
ENEA--Italian National Agency for New Technologies, Energy and the Environment Radiation Protection Institute, 16, via dei Colli, 40136 Bologna, Italy. guald@bologna.erea.it
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| pubmed:publicationType |
Journal Article,
Guideline,
Comparative Study,
Multicenter Study,
Evaluation Studies,
Validation Studies
|