Issue |
EPJ Nuclear Sci. Technol.
Volume 1, 2015
|
|
---|---|---|
Article Number | 2 | |
Number of page(s) | 9 | |
DOI | https://doi.org/10.1051/epjn/e2015-50041-5 | |
Published online | 27 November 2015 |
https://doi.org/10.1051/epjn/e2015-50041-5
Regular Article
Monte Carlo MSM correction factors for control rod worth estimates in subcritical and near-critical fast neutron reactors
1 Laboratoire de Physique Corpusculaire de Caen, ENSICAEN/Université de Caen/CNRS-IN2P3, 14050 Caen, France
2 SCK·CEN, Belgian Nuclear Research Centre, Boeretang 200, 2400 Mol, Belgium
3 Nuclear Fission Division, CIEMAT, Madrid, Spain
4 Laboratoire de Physique Subatomique et de Cosmologie, Université Grenoble-Alpes, CNRS/IN2P3, 53, rue des Martyrs, 38026 Grenoble Cedex, France
5 Institut de Physique Nucléaire d’Orsay, CNRS-IN2P3/Université Paris Sud, Orsay, France
6 Commissariat à l’Énergie Atomique et aux Énergies Alternatives, DEN, DER/SPEX, 13108 Saint-Paul-lez-Durance, France
* e-mail: lecouey@lpccaen.in2p3.fr
Received:
10
June
2015
Received in final form:
20
July
2015
Accepted:
10
August
2015
Published online:
27
November
2015
The GUINEVERE project was launched in 2006, within the 6th Euratom Framework Program IP-EUROTRANS, in order to study the feasibility of transmutation in Accelerator Driven subcritical Systems (ADS). This zero-power facility hosted at the SCK·CEN site in Mol (Belgium) couples the fast subcritical lead reactor VENUS-F with an external neutron source provided by interaction of deuterons delivered by the GENEPI-3C accelerator and a tritiated target located at the reactor core center. In order to test on-line subcriticality monitoring techniques, the reactivity of all the VENUS-F configurations used must be known beforehand to serve as benchmark values. That is why the Modified Source Multiplication Method (MSM) is under consideration to estimate the reactivity worth of the control rods when the reactor is largely subcritical as well as near-critical. The MSM method appears to be a technique well adapted to measure control rod worth over a large range of subcriticality levels. The MSM factors which are required to account for spatial effects in the reactor can be successfully calculated using a Monte Carlo neutron transport code.
© J.-L. Lecouey et al., published by EDP Sciences, 2015
This is an Open Access article distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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