Decay Heat Characterization for the European Sodium Fast Reactor

Abstract In this work a detailed assessment of the decay heat power for the commercial-size European Sodium-cooled Fast Reactor (ESFR) at the end of its equilibrium cycle has been performed. The summation method has been used to compute very accurate spatial- and time-dependent decay heat by employing state-of-the-art coupled transport-depletion computational codes and nuclear data. This detailed map provides basic information for subsequent transient calculations of the ESFR. A comprehensive analysis of the decay heat has been carried out and interdependencies among decay heat and different parameters characterizing the core state prior to shutdown, such as discharge burnup or type of fuel material, have been identified. That analysis has served as a basis to develop analytic functions to reconstruct the spatial-dependent decay heat power for the ESFR for cooling times within the first day after shutdown.

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Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4052190 ◽

2021 ◽

Author(s):

Janos Bodi ◽

Alexander Ponomarev ◽

Evaldas Bubelis ◽

Konstantin Mikityuk

Keyword(s):

Power Plant ◽

Fast Reactor ◽

Heat Removal ◽

Current Paper ◽

Decay Heat ◽

Sodium Fast Reactor ◽

Station Blackout ◽

Safety Assessments ◽

The Individual

Abstract As part of the ESFR-SMART project, safety assessments are being conducted on the updated European Sodium Fast Reactor (ESFR) design. An important part of the study is the evaluation of the reactor's behavior within hypothetical accidental conditions to assess and ensure that the accident would not lead to unexpected and disastrous events. In the current paper, the analyzed accidental scenario is the so called Protected Station Blackout (PSBO), where the offsite power is lost for the power plant, simulated by using the TRACE and SIM-SFR system codes. The assessment started from the simulation of the reactor behavior without the decay heat removal systems (DHRS). Following this, calculations of multiple DHRS arrangements have been performed to evaluate the individual and combined efficiency of the systems. Where it was possible, the results from the two system codes have been compared to show the consistency of the separate calculations. Through this study, the design of the DHRSs proposed at the beginning of the project have been investigated, and certain recommendations have been made for further improvement of the DHRS systems performance.

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Nuclear Data Uncertainty Propagation for a Sodium Fast Reactor

Journal of the Korean Physical Society ◽

10.3938/jkps.59.1191 ◽

2011 ◽

Vol 59 (2(3)) ◽

pp. 1191-1194 ◽

Cited By ~ 2

Author(s):

D. Rochman ◽

A. J. Koning ◽

D. F. Dacruz ◽

S. C. van der Marck

Keyword(s):

Fast Reactor ◽

Uncertainty Propagation ◽

Nuclear Data ◽

Data Uncertainty ◽

Sodium Fast Reactor

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Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor

Nuclear Data Sheets ◽

10.1016/j.nds.2014.04.127 ◽

2014 ◽

Vol 118 ◽

pp. 535-537

Author(s):

J.J. Herrero ◽

R. Ochoa ◽

J.S. Martínez ◽

C.J. Díez ◽

N. García-Herranz ◽

...

Keyword(s):

Fast Reactor ◽

Uncertainty Propagation ◽

Nuclear Data ◽

Data Uncertainty ◽

Sodium Fast Reactor ◽

Reactivity Coefficients

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New Reactor Safety Measures for the European Sodium Fast Reactor. Part II: Preliminary Assessment

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4051723 ◽

2021 ◽

Author(s):

Joel Guidez ◽

Janos Bodi ◽

Konstantin Mikityuk ◽

Enrico Girardi ◽

Jeremy Bittan ◽

...

Keyword(s):

Fast Reactor ◽

Heat Removal ◽

Reactor Safety ◽

Preliminary Assessment ◽

Safety Measures ◽

Decay Heat ◽

European Project ◽

Sodium Fast Reactor ◽

Core Catcher ◽

Gen Iv

Abstract The European project ESFR SMART offers innovative options of a sodium fast reactor to improve its safety. This paper explains the results of preliminary calculations made of the main options to verify the big lines of their feasibility. Design propositions and calculations are here provided of following innovative options: removal of the safety vessel, innovative decay heat removal systems, core catcher, thermal pumps and secondary loops. In conclusion, all these options seem able to fulfil the big lines of new safety rules for GEN-IV reactors. A status of the R&D necessary to validate these new options is also proposed.

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Nuclear data uncertainty propagation on a sodium fast reactor

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2017.08.018 ◽

2017 ◽

Vol 324 ◽

pp. 122-130 ◽

Cited By ~ 2

Author(s):

M. Griseri ◽

L. Fiorito ◽

A. Stankovskiy ◽

G. Van den Eynde

Keyword(s):

Fast Reactor ◽

Uncertainty Propagation ◽

Nuclear Data ◽

Data Uncertainty ◽

Sodium Fast Reactor

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Applying the Serpent-DYN3D code sequence for the decay heat analysis of metallic fuel sodium fast reactor

Annals of Nuclear Energy ◽

10.1016/j.anucene.2018.11.020 ◽

2019 ◽

Vol 125 ◽

pp. 291-306 ◽

Cited By ~ 3

Author(s):

G. Pereira ◽

A.E. Johnson ◽

Y. Bilodid ◽

E. Fridman ◽

D. Kotlyar

Keyword(s):

Fast Reactor ◽

Code Sequence ◽

Metallic Fuel ◽

Decay Heat ◽

Sodium Fast Reactor

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Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like sodium fast reactor

EPJ Web of Conferences ◽

10.1051/epjconf/201714609006 ◽

2017 ◽

Vol 146 ◽

pp. 09006

Author(s):

García-Herranz Nuria ◽

Panadero Anne-Laurène ◽

Martinez Ana ◽

Pelloni Sandro ◽

Mikityuk Konstantin ◽

...

Keyword(s):

Fast Reactor ◽

Nuclear Data ◽

Uncertainty Assessment ◽

Sodium Fast Reactor ◽

Reactivity Coefficients ◽

Data Sensitivity

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Recent advances in beta decay measurements

EPJ Nuclear Sciences & Technologies ◽

10.1051/epjn/2018034 ◽

2018 ◽

Vol 4 ◽

pp. 24

Author(s):

Magali Estienne ◽

Muriel Fallot ◽

Lydie Giot ◽

Loïc Le Meur ◽

Amanda Porta

Keyword(s):

Neutron Emission ◽

Uncertainty Propagation ◽

Fission Products ◽

Nuclear Data ◽

Summation Method ◽

Experimental Simulation ◽

Decay Data ◽

Decay Heat ◽

Systematic Effects ◽

Working Groups

Three observables of interest for present and future reactors depend on the β decay data of the fission products: the reactor decay heat, antineutrinos from reactors and delayed neutron emission. Concerning the decay heat, significant discrepancies still exist between summation calculations in − their two main ingredients: the decay data and the fission yields − performed using the most recent evaluated databases available. It has been recently shown that the associated uncertainties are dominated by the ones on the decay data. But the results subtantially differ taking into account or not the correlations between the fission products. So far the uncertainty propagation does not include as well systematic effects on nuclear data such as the Pandemonium effect which impacts a large number of nuclei contributing to the decay heat. The list of nuclei deserving new TAGS measurements has been updated recently in the frame of IAEA working groups. The issues listed above impact in the same way the predicted energy spectra of the antineutrinos from reactors computed with the summation method, the interest of which has been recently reinforced by the Daya Bay latest publication. Nuclear data should definitely contribute to refine and better control these calculations. Lastly, a lot of nuclear data related to delayed neutrons are missing in nuclear databases. Despite the progresses already done these last years with new measurements now requiring to be included in evaluated databases, the experimental efforts which still need to be done are significant. These different issues will be addressed here before to comment on recent experimental results and on their impacts on the quoted observables. Some perspectives will also be presented. Solving the issues listed above will require to bring together experimental, simulation, evaluation and theoretical activities.

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