Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13

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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A Numerical Design and Feasibility Study of Self-Wastage Experiment Using Simulant Material in a Sodium Fast Reactor

Nuclear Engineering and Technology ◽

10.1016/j.net.2015.12.006 ◽

2016 ◽

Vol 48 (2) ◽

pp. 368-375

Author(s):

Sunghyon Jang ◽

Takashi Takata ◽

Akira Yamaguchi

Keyword(s):

Feasibility Study ◽

Fast Reactor ◽

Sodium Fast Reactor ◽

Numerical Design

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Heterogeneous Transmutation Sodium Fast Reactor

10.2172/920415 ◽

2007 ◽

Author(s):

S. E. Bays

Keyword(s):

Fast Reactor ◽

Sodium Fast Reactor

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Simplified modeling of liquid sodium medium with temperature and velocity gradient using real thermal-hydraulic data. Application to ultrasonic thermometry in sodium fast reactor

10.1063/1.4789245 ◽

2013 ◽

Cited By ~ 2

Author(s):

N. Massacret ◽

J. Moysan ◽

M. A. Ploix ◽

J. P. Jeannot ◽

G. Corneloup

Keyword(s):

Fast Reactor ◽

Velocity Gradient ◽

Liquid Sodium ◽

Sodium Fast Reactor ◽

Data Application ◽

Simplified Modeling

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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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New Reactor Safety Measures for the European Sodium Fast Reactor - Part I: Conceptual Design

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4051364 ◽

2021 ◽

Author(s):

Joel Guidez ◽

Janos Bodi ◽

Konstantin Mikityuk ◽

Enrico Girardi ◽

Bernard Carluec

Keyword(s):

Fast Reactor ◽

Heat Removal ◽

Thermal Inertia ◽

Lessons Learned ◽

Reactor Safety ◽

Fukushima Accident ◽

Safety Level ◽

Safety Measures ◽

Sodium Fast Reactor ◽

High Thermal Inertia

Abstract Following up the previous CP-ESFR project, the ESFR-SMART project considers the safety objectives envisaged for Generation-IV reactors, taking into account the lessons learned from the Fukushima accident, in order to increase the safety level of the European Sodium Fast Reactor (ESFR). In accordance with these objectives, guidelines have been defined to drive the ESFR-SMART developments, mainly simplifying the design and using all the positive features of Sodium Fast Reactors (SFR), such as low coolant pressure, efficiency of natural convection, possibility of decay heat removal (DHR) by atmospheric air, high thermal inertia and long grace period before a human intervention is needed. In this paper, a set of new ambitious safety measures is introduced for further evaluation within the project. The proposed set aims at consistency with the main lines of safety evolutions since the Fukushima accident, but it does not yet constitute the final comprehensive safety analysis. The paper gives a first review of the new propositions to enhance the ESFR safety, leading to a simplified reactor, forgiving and including a lot of passivity. This first version is supported by the various project tasks in order to assess the relevance of the whole design in comparison to the final safety objectives.

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