EPJ Web of Conferences
Volume 106, 2016ISRD 15 – International Symposium on Reactor Dosimetry
|Number of page(s)||6|
|Section||Cross Sections, Nuclear Data and Uncertainties|
|Published online||03 February 2016|
Generation of 238U Covariance Matrices by Using the Integral Data Assimilation Technique of the CONRAD Code
1 CEA, DEN Cadarache, 13108 Saint Paul Les Durance, France
2 NAPC-Nuclear Data Section, International Atomic Energy Agency, P.O. Box 100, Vienna A-1400, Austria
a Corresponding author: firstname.lastname@example.org
Published online: 3 February 2016
A new IAEA Coordinated Research Project (CRP) aims to test, validate and improve the IRDF library. Among the isotopes of interest, the modelisation of the 238U capture and fission cross sections represents a challenging task. A new description of the 238U neutrons induced reactions in the fast energy range is within progress in the frame of an IAEA evaluation consortium. The Nuclear Data group of Cadarache participates in this effort utilizing the 238U spectral indices measurements and Post Irradiated Experiments (PIE) carried out in the fast reactors MASURCA (CEA Cadarache) and PHENIX (CEA Marcoule). Such a collection of experimental results provides reliable integral information on the (n,γ) and (n,f) cross sections. This paper presents the Integral Data Assimilation (IDA) technique of the CONRAD code used to propagate the uncertainties of the integral data on the 238U cross sections of interest for dosimetry applications.
© Owned by the authors, published by EDP Sciences, 2016
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