Report on intermediate results of the IAEA CRP on ‘Studies of advanced reactor technology options for effective incineration of radioactive waste’

Maschek, W.; Stanculescu, A.; Ariën, B.; Bai, Yu; Chabert, C.; Chebeskov, A. A.; Chen, X.; Cruz, D. F. Da; Dekoussar, V.; Devan, K.; Dulla, Sandra; Gopalakrishnan, V.; Feynberg, O.; Harish, R.; Ignatiev, V.; Kópházi, J.; Li, J.; Malambu, E.; Mohanakrishnan, P.; Morita, Koji; Pandikumar, G.; Pénéliau, Y.; Ravetto, Piero; Rineiski, A.; Schikorr, M.; Srivenkatesan, R.; Subbotin, V. G.; Surenkov, A. I.; Szieberth, M.; Taczanowski, S.; Kamil, Tucek; Vertes, P.; Vorotyntsev, M.F.; Uhlíř, Jan; Wider, H.U.; Wu, Yican; Zakirov, R. Ya.; Zheng, Suqing

doi:10.1016/j.enconman.2007.08.018

Cited by 24 publications

(8 citation statements)

References 12 publications

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“…The MOSART fuel circuit and reactor configuration are represented in Ignatiev et al (2006) and Maschek et al (2008). Here, the reactor configuration is displayed in Fig.…”

Section: Numerical Simulation Of Ulof For Mosartmentioning

confidence: 99%

“…The second one is the modified point kinetic model (referred as MPKM), which is derived by MacPhee (1958) considering the decay of neutron precursors in the out loop as shown below…”

Section: Approximated Kinetic Models For Comparisonmentioning

confidence: 99%

“…The lumped parameter model is adopted for heat transfer calculation in the core based on the energy conservation principle (MacPhee, 1958;Zhang et al, 2009a). The energy balance equation for the liquid fuel has the form…”

Section: Heat Transfer Modelmentioning

confidence: 99%

“…The developed spatial kinetic model is applied to the ULOF numerical calculation based on the MOSART conceptual design, which was developed for burning spent nuclear fuel. The other two simplified models in Merle-Lucotte et al (2008) and MacPhee (1958) are also adopted for comparison. The steady state calculation shows that the fuel flow influences the distributions of the delayed neutron precursors significantly.…”

Section: Introductionmentioning

confidence: 99%

“…The simplest option (Merle-Lucotte et al, 2008) is to only modify the original effective delayed neutron fraction b eff byb eff in the conventional point kinetic equations, while the equations for the effective delayed neutron precursors are the same as those for solid-fuel reactors. A more complex model (MacPhee, 1958) leads to modification of the calculating procedure for computing effective delayed neutron precursors c i (t), in which equations for the effective precursors are modified in order to account explicitly for their decay out of the core. Rineiski et al proposed a general model, in which the spatial distribution of the precursors is modeled and then the effective precursors (employed in the point kinetic part that serves for accelerating spatial kinetic calculations) are computed by averaging these spatial distributions while using the adjoint neutron flux as weighting function (Rineiski et al, 2005).…”

Section: Introductionmentioning

confidence: 99%

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Development of a kinetic model for safety studies of liquid-fuel reactors

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“…The MOSART fuel circuit and reactor configuration are represented in Ignatiev et al (2006) and Maschek et al (2008). Here, the reactor configuration is displayed in Fig.…”

Section: Numerical Simulation Of Ulof For Mosartmentioning

confidence: 99%

“…The second one is the modified point kinetic model (referred as MPKM), which is derived by MacPhee (1958) considering the decay of neutron precursors in the out loop as shown below…”

Section: Approximated Kinetic Models For Comparisonmentioning

confidence: 99%

Section: Heat Transfer Modelmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations