Abstract In the framework of the GUINEVERE project (Generation of Uninterrupted Intense NEutrons at the lead VEnus REactor) carried out at SCK⋅CEN in Mol, the continuous deuteron accelerator GENEPI-3C is coupled to the VENUS-F fast simulated lead-cooled reactor. With this installation the neutronic behaviour of an Accelerator Driven System (ADS) during different phases of operation is studied. Because of the subcritical character of ADS, an on-line reactivity monitoring system is required. The main goal of the GUINEVERE project is to design such a system, to evaluate its performance and accuracy, and to evaluate an extrapolation towards full-size ADS. The on-line subcriticality monitoring procedure within the GUINEVERE project requires a well-known critical reference state in order to determine the absolute subcriticality level of ADS. Direct absolute subcriticality measurement techniques can then be evaluated. The neutronic design of different types of critical configurations within the VENUS vessel is motivated, given the core fuel and lead reflector as basic elements. The neutronic analysis comprises operational aspects such as kinetic parameters, the weight of control and safety rods, the weight of a peripheral assembly, which are investigated by means of both probabilistic and deterministic neutronic codes. The outcome of this analysis determines the most suitable VENUS-F critical reference core. Critical reference configurations inside the VENUS vessel can be set-up with the available fuel (96 fuel assemblies) taking into account the uncertainty on the nuclear data. The flexible neutronic design allows an easy operation of the core. A sensitivity analysis on the nuclear data shows that an uncertainty corresponding to the weight of several peripheral fuel assemblies should be taken into account while designing this type of small cores.
[1]
G. Granget,et al.
The GENEPI-3C Accelerator for the GUINEVERE Project
,
2009
.
[2]
R. K. Meulekamp,et al.
Calculating the Effective Delayed Neutron Fraction with Monte Carlo
,
2006
.
[3]
H. Takano,et al.
Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3
,
2002
.
[4]
Philip R. Page,et al.
ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
,
2006
.
[5]
B. Verboomen,et al.
An Optimum Approach to Monte Carlo Burnup
,
2007
.
[6]
Gérald Rimpault,et al.
THE ERANOS CODE AND DATA SYSTEM FOR FAST REACTOR NEUTRONIC ANALYSES
,
2002
.
[7]
H. Nifenecker,et al.
ACCELERATOR DRIVEN SUBCRITICAL REACTORS.
,
2003
.
[8]
A. Hogenbirk,et al.
New Nuclear Data Libraries for Lead and Bismuth and Their Impact on Accelerator-Driven Systems Design
,
2007
.
[9]
M. M. Bretscher.
Evaluation of reactor kinetic parameters without the need for perturbation codes.
,
1998
.
[10]
B. Verboomen,et al.
Monte Carlo Calculation of the Effective Neutron Generation Time
,
2006
.
[11]
Arkady Serikov,et al.
Design study of a fast spectrum zero-power reactor dedicated to source driven sub-critical experiments
,
2010
.
[12]
G. Rimpault,et al.
Neutronic Studies in Support of Accelerator-Driven Systems: The MUSE Experiments in the MASURCA Facility
,
2004
.
[13]
G. Rimpault,et al.
The GUINEVERE project at the VENUS facility
,
2008
.