The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)

Sarotto, M.; Castelliti, D.; Fernandez, R.; Lamberts, Damien; Malambu, E.; Stankovskiy, Alexey; Jaeger, Wadim; Ottolini, Marco; Martín-Fuertes, F.; Sabathé, Laurent; Mansani, L.; Baeten, P.

doi:10.1016/j.nucengdes.2013.08.055

Cited by 34 publications

(18 citation statements)

References 9 publications

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“…The coolant outlet temperature is searched to ensure that the maximum coolant velocity during the operational cycle is less than 2.0 m/s to limit the erosion effects (Mansani et al, 2012;Sarotto et al, 2013;Mukaiyama et al, 2001;Song et al, 2007). The coolant outlet temperature is almost proportional to the thermal power as shown in Table 4.…”

Section: Thermal Power and Cycle Lengthmentioning

confidence: 99%

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

Zhou

Zheng

et al. 2015

Nuclear Engineering and Design

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Section: Thermal Power and Cycle Lengthmentioning

confidence: 99%

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

Zhou

Zheng

et al. 2015

Nuclear Engineering and Design

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“…The MYRRHA-FASTEF critical core dimensions (version 1.4) have been established and the main geometrical parameters have been summarized in Sarotto and et al (2013). The core consists of five types of S/As (sub-assemblies): 70 original fuel assemblies, 6 IPS (In Pile Section) assemblies, 6 control rod assemblies and 3 shut-down rod assemblies, 1 ring of 24 inner dummy assemblies (hexcan structure and LBE) and 1 ring of 42 outer dummy assemblies (YZrO or steel rods) enclosed in a barrel of 1470 mm outer diameter and 40 mm thickness.…”

Section: Myrrha-fastef Critical Core Designmentioning

confidence: 99%

Studies of fuel dispersion after pin failure: Analysis of assumed blockage accidents for the MYRRHA–FASTEF critical core

Chen

Rineiski

et al. 2015

Annals of Nuclear Energy

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“…In the latter configuration, the reactor is coupled with a proton accelerator and operated as Accelerator Driven System (ADS), where the LBE coolant is also used as spallation target for neutron production. The planned nuclear fuel in the subcritical mode is a uraniumeplutonium mixed oxide (MOX) containing 30% of PuO 2 [4].…”

Section: Introductionmentioning

confidence: 99%

Interaction study between MOX fuel and eutectic lead–bismuth coolant

Vigier

Popa

Tyrpekl

et al. 2015

Journal of Nuclear Materials

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h i g h l i g h t s g r a p h i c a l a b s t r a c t Interaction tests are performed between U 0.7 Pu 0.3 O 2 fuel and Pb 0.45 Bi 0.55 liquid metal coolant. Oxygen concentration in liquid metal, stoichiometry of the MOX and interaction temperature are studied. No chemical reaction detected. Less than 0.01% to 0.65% of the pellets is released into the coolant depending to the conditions. a b s t r a c tIn the frame of the MYRRHA reactor project, the interaction between fuel pellets and the reactor coolant is essential for safety evaluations, e.g. in case of a pin breach. Therefore, interaction tests between uraniumeplutonium mixed oxide (MOX) pellets and molten lead bismuth eutectic (LBE) have been performed and three parameters were studied, namely the interaction temperature (500 C and 800 C), the oxygen content in LBE and the stoichiometry of the MOX (U 0.7 Pu 0.3 O 2Àx and U 0.7 Pu 0.3 O 2.00 ). After 50 h of interaction in closed containers, the pellet integrity was preserved in all cases. Whatever the conditions, neither interaction compounds (crystalline or amorphous) nor lead and bismuth diffusion into the surface regions of the MOX pellets has been detected. In most of the conditions, actinide releases into LBE were very limited (in the range of 0.01e0.15 mg), with a homogeneous release of the different actinides present in the MOX. Detected values were significantly higher in the 800 C and low LBE oxygen content tests for both U 0.7 Pu 0.3 O 2Àx and U 0.7 Pu 0.3 O 2.00 , with 1e2 mg of actinide released in these conditions.

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The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)

Cited by 34 publications

References 9 publications

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

Preliminary studies of a new accelerator-driven minor actinide burner in industrial scale

Studies of fuel dispersion after pin failure: Analysis of assumed blockage accidents for the MYRRHA–FASTEF critical core

Interaction study between MOX fuel and eutectic lead–bismuth coolant

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