Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations G Noguere1, O Bouland1, D Bernard1, P Leconte1, P Blaise1,
epjconf wond
Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations 27 Sept 2012 Wonder 2012 G Noguere, O Bouland, D Bernard, P
Noguere
MOX-use is today a mature business and continuous improvement is in matching two main The imbalance between the separation and use of plutonium as MOX fuel had resulted in 2010 [2,3] There are plans for the construction of a new MOX plant calculate the core physics performance of such plutonium A second
UOj fuel, because Pu content of MOX fuel for Pu thermal utilization is low new code system is to be applied to treat the heterogeneity in MOX fuel assembly and the neutron In order to improve Pu thermal utilization in future, various R D program on fuel design and nuclear design are being performed, such as the
the DAMPIERRE PWR reactor using the latest versions of the JEFF European nuclear data li- performed in France and shows the improvement given by JEFF3 0 in the build-up, to larger Pu amount and higher burnups in MOx fuels The APOLLO2 depletion calculation scheme of MOx assemblies is based on the UP1
Inert gas behaviour: a new model based on a mechanistic approach coupling gas 2 1 Improved model for thermal expansion A novel correlation for the Young's modulus (E, GPa) of MOX fuel as a function of Pu content, porosity, the new correlation for the thermal conductivity of MOX Regressor Units Estimate A0
INSPYRE D . v Incorporation and verification of models and properties in codes
this plutonium in MOX fuel is now under consideration. The Technical Committee Meeting on Recycling of Plutonium and Uranium in Water. Reactor Fuel was
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configurations of MOX fuel assemblies • The parameter of interest in this work is the residual reactivity • New reactivity calculations using the TRIPOLI-4 Monte-Carlo Code with the JEFF-3 1 1 nuclear data library have confirmed the systematic overestimation of the keff
performing calculations using the average Pu-content and calculations using the real heterogeneous representations The comparisons made cover two configurations: • infinite lattice of fuel assemblies of the same type • fuel assemblies loaded in a transport cask The study is divided into different steps the main ones being:
(MOX) fuel con?gurations were carried out in the zero- power reactor EOLE of Commissariat a` l’énergie atom- ique et aux énergies alternatives (CEA) Cadarache France
Lattice Physics calculations using t-depl • The t-depl sequence of TRITON couples 2-D NEWT calculations with multiple ORIGEN-S calculations to provide a robust and accurate depletion method with
MOX utilisation in PWRs with plutonium both of typical and poor isotopic quality The typical type is a plutonium isotopic vector with higher fissile fraction using commercial PWR MOX The latter type is a plutonium of low isotopic vector expected for a self-generation recycling mode in PWR MOX
How is MOX fuel made?
- MOX fuel can be made by grinding together uranium oxide (UO 2) and plutonium oxide (PuO 2) before the mixed oxide is pressed into pellets, but this process has the disadvantage of forming much radioactive dust.
What is the difference between MOX and Pu-239?
- This gives fuel with about 1% Pu-239 and 4% U-235 which can sustain burn-up of 50 GWd/t over four years and has similar characteristics to normal LWR fuel. It is distinct from MOX in having low and incidental levels of plutonium – none is added.
How much plutonium is in MOX fuel?
- MOX fuel, consisting of about 7-11% plutonium mixed with depleted uranium, is equivalent to uranium oxide fuel enriched to about 4.5% U-235, assuming that the plutonium has about two-thirds fissile isotopes. If weapons plutonium is used (>90% Pu-239), only about 5% plutonium is needed in the mix.
How much MoX does a nuclear reactor use?
- Most reactors use it as about one third of their core, but some will accept up to 50% MOX assemblies. In France, EDF aims to have all its 900 MWe series of reactors running with at least one-third MOX. Japan aimed to have one third of its reactors using MOX by 2010, and has approved construction of a new reactor with a complete fuel loading of MOX.
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