TY - JOUR
T1 - Analysis of the comparison of in situ measurements made on biological shielding of the BR3 nuclear reactor
AU - Crozet, Marielle
AU - Demeyer, Séverine
AU - Lourenco, Valérie
AU - Herranz, Margarita
AU - Boden, Sven
N1 - Score=10
PY - 2022/5/5
Y1 - 2022/5/5
N2 - INSIDER (Improved Nuclear SIte characterization for waste minimization in D&D operations under constrained EnviRonment) was a European project funded under the H2020-EURATOM programme and launched in June 2017. The project was coordinated by the French Commissariat à l’énergie atomique et aux énergies alternatives (CEA), it had a total duration of 4 years and covered a budget of 4 M€. INSIDER’s work was performed by 5 technical working groups (WG) which brought together 18 institutions from 10 countries, leading to a total of 68 participating researchers. The objective of the project was to optimise the radiological characterisation of nuclear installations in constrained environments in order to obtain an accurate estimate of the content of contaminated materials as well as to optimise the quantity of contaminated materials to be treated as waste. The focus of this paper is on the statistical analysis of an interteam comparison of measurement results (dose rate, total gamma measurement, and gamma spectrometry) made in situ at the BR3 reactor, Belgium.
AB - INSIDER (Improved Nuclear SIte characterization for waste minimization in D&D operations under constrained EnviRonment) was a European project funded under the H2020-EURATOM programme and launched in June 2017. The project was coordinated by the French Commissariat à l’énergie atomique et aux énergies alternatives (CEA), it had a total duration of 4 years and covered a budget of 4 M€. INSIDER’s work was performed by 5 technical working groups (WG) which brought together 18 institutions from 10 countries, leading to a total of 68 participating researchers. The objective of the project was to optimise the radiological characterisation of nuclear installations in constrained environments in order to obtain an accurate estimate of the content of contaminated materials as well as to optimise the quantity of contaminated materials to be treated as waste. The focus of this paper is on the statistical analysis of an interteam comparison of measurement results (dose rate, total gamma measurement, and gamma spectrometry) made in situ at the BR3 reactor, Belgium.
KW - INSIDER project
KW - BR3 reactor
KW - Proficiency test
KW - Analysis of variance
UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/53528408
U2 - 10.1007/s10967-022-08319-9
DO - 10.1007/s10967-022-08319-9
M3 - Article
SN - 0236-5731
VL - 331
SP - 2967
EP - 2982
JO - Journal of Radioanalytical and Nuclear Chemistry
JF - Journal of Radioanalytical and Nuclear Chemistry
ER -