Euradwaste '08 - EU Bookshop - Europa
Euradwaste '08 - EU Bookshop - Europa Euradwaste '08 - EU Bookshop - Europa
Table 6: FUTURIX FTA fuels Fuel name Fuel Composition Max. linear power T° max. estimated (W/cm) (°C) DOE 1 U0,24Pu0,2Am0,03Np0,01Zr0,52 350 940 DOE 2 Pu0,29Am0,07Zr0,64 440 1050 DOE 3 U0,5Pu0,25Am0,15Np0,10N 370 1010 DOE 4 Pu0,23Am0,04Zr0,73N 290 830 ITU 5 Pu0,80Am0,20O2-x + 86 vol%Mo 140 1590 ITU 6 Pu0,23Am0,24Zr0,53O2-x + 60 vol%Mo 130 1510 CEA 7 Pu0,5Am0,5O2-x + 80 vol%MgO 100 1420 CEA 8 Pu0,8Am0,2O2-x +75 vol%MgO 80 1260 A metal matrix (Mo) provides an excellent possibility to obtain composite fuels with highest thermal conductivity, and ultimately can permit highest actinide loading in the fuel. Mo must be enriched in 92 Mo to ensure no neutronic penalties, or eventual build up of Tc. Currently, four such fuel samples are under irradiation in the FUTURIX FTA (Phénix) and HELIOS (HFR Petten) irradiation programmes. 2.5 Experimental qualification of the on-line monitoring of a sub-critical core configuration The GUINEVERE project will provide answers to the questions of on-line reactivity monitoring, sub-criticality determination and establishment of operational procedures for ADS [11]. A continuous beam is needed for validation of the reactivity monitoring and it is necessary to establish a more complete data base for a pure lead core. To meet these requirements SCK/CEN modifies the VE- NUS critical facility located at the Mol site as follows: Development of a new GENEPI-C accelerator operating in continuous and pulsed mode. Installation of the accelerator at the VENUS facility and coupling to the new core. Adaptation of the VENUS facility to host a fast lead core which will be named VENUS-F. Based on the experience of GENEPI 1-2 development and operation, a new GENEPI-C accelerator is being developed for continuous and pulsed mode operation. To realise the intended beam trips the performance of prompt beam interruptions are foreseen with a repetition rate of a fraction of 1 Hz and duration of beam interrupts between a few hundreds �s and a few tens of ms. The necessary development is carried out at the CNRS laboratories in Grenoble. A sub-critical core will use two different types of fuel loading in a unique assembly type. It is foreseen to start the operation of the zero power facility in a critical mode configuration which necessitates a shut-down system that provides sufficient shut-down reactivity insertion in a time interval that is sufficiently short to stop the chain reaction before core damage occurs. Moreover the system has to be intrinsically safe. Therefore, a system has been chosen with the shut-down rods allocated at the periphery of the fissile fuel assemblies. The rods fall into the core under gravity when receiving the signal to de-energize electro-magnets which keep the rods out of the core region. Such a system was already installed at the VENUS facility during the first years of operation. 3. Concluding remarks 122
In the course of the development of new designs for nuclear systems for transmutation it became obvious that a successful introduction of these systems needs further design optimization. However, part of the information needed for the design specifications is still uncertain and therefore design solutions have to consider rather large uncertainties in the design process. For example, if an economically acceptable solution for an ADS system is envisaged it becomes necessary to launch a broad R&D program ranging from evaluation of open material property issues to basic features of the reliable operation of such a complex system. As result of the European research effort around the EUROTRANS project first answers to the most relevant open questions will be obtained. The development of MA bearing fuels is still at a very early stage, and will require substantial effort in the future. A recent road mapping exercise (EISOFAR) has shown quite clearly that a new SFR deployed in 2020 will necessarily be fuelled with MOX fuel. This reactor together with the XT- ADS plant can then be used as an instrument to test and qualify fuels bearing MA in homogeneous or heterogeneous recycling modes. In the meantime the fabrication, critical property determination and irradiation testing dedicated to specific effects are necessary for the down selection of options. Furthermore, the development of multidimensional theoretical approaches will also contribute to an improved understanding of fuel behaviour, and thereby improved means to design essential experiments along with a reduction in their number and concomitant costs. References: [1] C.Fazio, M.Salvatores and W.S.Yang, “Down-selection of partitioning routes and of transmutation fuels for P/T strategies implementation”, Proc. Int. Conf. GLOBAL 2007, Boise, Sept. 2007 [2] C. Prunier, F. Boussard, L. Koch, M. Coquerelle, "Some specific aspects of homogeneous Am and Np based transmutation fuels through the outcomes of the SUPERFACT experiment in the Phénix reactor", Proc. Global 1993, Seattle, September 1993. [3] C.T. Walker, G. Nicolaou, "Transmutation of Np and Am in a fast neutron flux: EPMA results and KORIGEN predictions for the SUPERFACT fuels", J. Nucl. Mater., 218(1995)129 [4] J. Knebel et. Al: “European research programme for the transmutation of high level nuclear waste in an accelerator driven system – EUROTRANS” Proc. FISA 2006 Luxemburg (March 2006) EUR 21231 [5] A. C. Mueller: “The PDS-XADS Reference Accelerator” International Workshop on P&T and ADS Development, October 2003, SCK•CEN Mol, Belgium. [6] P. Pierini: “ADS Reliability Activities in Europe”, 4th OECD NEA International Workshop on Utilization and Reliability of HPPA, May 2004, Daejon, Rep. of Korea. [7] J-L. Biarrotte et al.: “A reference accelerator scheme for ADS applications”, International Conference on Accelerator Applications, August 2005, Venice, Italy. [8] R.J.M. Konings, R. Conrad, G. Dasel, B.J. Pijlgroms, J. Somers and E. Toscano, "The EFT- TRA-T4 experiment on americium transmutation", J. Nucl. Mater., 282(2000)159. [9] Ch. Hellwig, M. Streit, P. Blair, T. Tverberg, F.C. Klaassen, R.P.C. Schram, F. Vettraino, T. Yamashita, "Inert matrix fuel behaviour in test irradiations", Journal of Nuclear Materials 352 (2006) 291–299 [10] G.Gaillard-Groléas, F.Sudreau, D.Warin, "PHENIX Irradiation Program on Fuels and Targets for Transmutation", Proc. Global 2003, New Orleans, December 2003. [11] P. Baeten et.al.: “The “GUINEVERE“ project at the VENUS facility” Proc. HPPA’05 on “Utilisation and Reliability of High Power Proton Accelerators” Mol, Belgium (May 2007) 123
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Table 6: FUTURIX FTA fuels<br />
Fuel name Fuel Composition<br />
Max. linear power T° max. estimated<br />
(W/cm) (°C)<br />
DOE 1 U0,24Pu0,2Am0,03Np0,01Zr0,52 350 940<br />
DOE 2 Pu0,29Am0,07Zr0,64 440 1050<br />
DOE 3 U0,5Pu0,25Am0,15Np0,10N 370 1010<br />
DOE 4 Pu0,23Am0,04Zr0,73N 290 830<br />
ITU 5 Pu0,80Am0,20O2-x + 86 vol%Mo 140 1590<br />
ITU 6 Pu0,23Am0,24Zr0,53O2-x + 60 vol%Mo 130 1510<br />
CEA 7 Pu0,5Am0,5O2-x + 80 vol%MgO 100 1420<br />
CEA 8 Pu0,8Am0,2O2-x +75 vol%MgO 80 1260<br />
A metal matrix (Mo) provides an excellent possibility to obtain composite fuels with highest thermal<br />
conductivity, and ultimately can permit highest actinide loading in the fuel. Mo must be enriched<br />
in 92 Mo to ensure no neutronic penalties, or eventual build up of Tc. Currently, four such fuel<br />
samples are under irradiation in the FUTURIX FTA (Phénix) and HELIOS (HFR Petten) irradiation<br />
programmes.<br />
2.5 Experimental qualification of the on-line monitoring of a sub-critical core configuration<br />
The GUINEVERE project will provide answers to the questions of on-line reactivity monitoring,<br />
sub-criticality determination and establishment of operational procedures for ADS [11]. A continuous<br />
beam is needed for validation of the reactivity monitoring and it is necessary to establish a more<br />
complete data base for a pure lead core. To meet these requirements SCK/CEN modifies the VE-<br />
NUS critical facility located at the Mol site as follows:<br />
Development of a new GENEPI-C accelerator operating in continuous and pulsed mode.<br />
Installation of the accelerator at the VENUS facility and coupling to the new core.<br />
Adaptation of the VENUS facility to host a fast lead core which will be named VENUS-F.<br />
Based on the experience of GENEPI 1-2 development and operation, a new GENEPI-C accelerator<br />
is being developed for continuous and pulsed mode operation. To realise the intended beam trips<br />
the performance of prompt beam interruptions are foreseen with a repetition rate of a fraction of 1<br />
Hz and duration of beam interrupts between a few hundreds �s and a few tens of ms. The necessary<br />
development is carried out at the CNRS laboratories in Grenoble.<br />
A sub-critical core will use two different types of fuel loading in a unique assembly type. It is foreseen<br />
to start the operation of the zero power facility in a critical mode configuration which necessitates<br />
a shut-down system that provides sufficient shut-down reactivity insertion in a time interval<br />
that is sufficiently short to stop the chain reaction before core damage occurs. Moreover the system<br />
has to be intrinsically safe. Therefore, a system has been chosen with the shut-down rods allocated<br />
at the periphery of the fissile fuel assemblies. The rods fall into the core under gravity when receiving<br />
the signal to de-energize electro-magnets which keep the rods out of the core region. Such a<br />
system was already installed at the VENUS facility during the first years of operation.<br />
3. Concluding remarks<br />
122