scholarly journals France–Japan synthesis concept on sodium-cooled fast reactor review of a joint collaborative work

2021 ◽  
Vol 7 ◽  
pp. 15
Author(s):  
Gilles Rodriguez ◽  
Frédéric Varaine ◽  
Laurent Costes ◽  
Christophe Venard ◽  
Frédéric Serre ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Collaborative Work ◽  
Design Concept ◽  
National Standards ◽  
Second Phase ◽  
Joint Work ◽  
Sodium Fast Reactor ◽  
Working Groups ◽  
Design Requirements ◽  
Collaboration Agreement

In the frame of the France-Japan agreement on nuclear collaboration, a bilateral collaboration agreement on nuclear energy was signed on March 21st, 2017, including a topic dedicated to Sodium-cooled Fast Reactor (SFR). This agreement has set the framework to start a bilateral discussion on a joint view of an SFR concept. France (CEA and FRAMATOME) and Japan (JAEA, MHI and MFBR) have carried out these studies from 2017 to 2019. Based on the beginning of the basic design phase of ASTRID project − ASTRID − 600 MWe (ASTRID for Advanced Sodium Technological Reactor for Industrial Demonstration), the two countries performed a common work to examine ways to develop a feasible common design concept, which could be realized both in France and in Japan. The subject was then extended and extrapolated with the ASTRID − 150 MWe data (reduced power reactor and enhanced experimental capabilities) in a second phase of this study. France and Japan first focused on design requirements. Common requirements were identified, as well as differences in the safety approach and the structural design requirements, according to national standards and respective site conditions, in particular considering seismic hazards. The teams developed common Top-Level design Requirements (TLRs) to allow common specification data, then joint design. This collaborative work was carried out through the implementation of twelve France-Japan Working Groups, working jointly. This paper is providing a review of this joint synthesis on Sodium Fast Reactor design concept. It is summarizing the context and objectives, then the definition and approaches of the Top Level Requirements. This paper is then dealing with the major design features: the core design and their related safety aspects, and the nuclear island design. Thus, this paper is providing a comprehensive review of this joint work gathering French and Japan nuclear design teams during two full years.

Large Electro-Magnetic Pump Design for Application in the ASTRID Sodium-Cooled Fast Reactor

2014 ◽  
Author(s):  
Rie Aizawa ◽  
Tetsu Suzuki ◽  
Guy Laffont ◽  
Frédéric Rey
Keyword(s):  
Fast Reactor ◽  
High Efficiency ◽  
Operating Conditions ◽  
Joint Work ◽  
Main Concept ◽  
Pump Design ◽  
Sodium Fast Reactor ◽  
Technological Developments ◽  
Electro Magnetic ◽  
Collaboration Agreement

Within the framework of the French Sodium Fast Reactor (SFR) prototype called ASTRID (Advance Sodium Technological Reactor for Industrial Demonstration), an application of Large capacity Electro-Magnetic Pumps (LEMP) is considered as a main concept of the circulating pump on intermediate sodium circuits. The use of LEMP has several merits in the design of reactor, operation, and maintenance. Furthermore, high efficiency is acquired when heat-resistant coil insulation is used for this LEMP. Nevertheless, some theoretical and technological developments have to be carried out in order to validate the design tools by taking into account Magneto Hydro Dynamic (MHD) phenomena and the applicability of the LEMP to ASTRID steady state and transient operating conditions. In this aim, a collaboration agreement between the CEA and TOSHIBA Corporation came into force in April 2012 to carry out a joint work program on the ASTRID EMP design and development. This paper describes the dedicated design studies and experimental activities for the LEMP development within the framework of the CEA-TOSHIBA collaboration.

Design and first operation of the MACARON irradiation experiment of Sodium Fast reactor absorber pins in the BOR-60 reactor

2021 ◽  
Vol 135 ◽  
pp. 103676
Author(s):  
T. Lambert ◽  
J.M. Escleine ◽  
B. Fontaine ◽  
S. Eremin ◽  
E. Muraleva ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Irradiation Experiment ◽  
Sodium Fast Reactor

scholarly journals Developing a quality management system for the European Network for Health Technology Assessment (EUnetHTA): toward European HTA collaboration

2021 ◽  
Vol 37 (1) ◽  
Author(s):  
Miriam Luhnen ◽  
Sari Susanna Ormstad ◽  
Anne Willemsen ◽  
Chaienna Schreuder-Morel ◽  
Catharina Helmink ◽  
...  
Keyword(s):  
Quality Management ◽  
Health Technology Assessment ◽  
Technology Assessment ◽  
Management System ◽  
Quality Management System ◽  
Health Technology ◽  
European Network ◽  
Joint Work ◽  
Working Groups ◽  
Assessment Reports

Abstract Objectives The European Network for Health Technology Assessment (EUnetHTA) was established in 2006 and comprises over eighty organizations from thirty European countries. In its fifth project phase (Joint Action 3), EUnetHTA set up a quality management system (QMS) to improve the efficiency and standardization of joint work. This article presents EUnetHTA's new QMS and outlines experiences and challenges during its implementation. Methods Several working groups defined processes and methods to support assessment teams in creating high-quality assessment reports. Existing guidelines, templates, and tools were refined and missing parts were newly created and integrated into the new QMS framework. EUnetHTA has contributed to Health Technology Assessment (HTA) capacity building through training and knowledge sharing. Continuous evaluation helped to identify gaps and shortcomings in processes and structures. Results Based on a common quality management concept and defined development and revision procedures, twenty-seven partner organizations jointly developed and maintained around forty standard operating procedures and other components of the QMS. All outputs were incorporated into a web-based platform, the EUnetHTA Companion Guide, which was launched in May 2018. Concerted efforts of working groups were required to ensure consistency and avoid duplication. Conclusions With the establishment of a QMS for jointly produced assessment reports, EUnetHTA has taken a significant step toward a sustainable model for scientific and technical collaboration within European HTA. However, the definition of processes and methods meeting the numerous requirements of healthcare systems across Europe remains an ongoing and challenging task.

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

2021 ◽  
Vol 164 ◽  
pp. 108600
Author(s):  
Shibao Wang ◽  
Konstantin Mikityuk ◽  
Petrovic Dorde ◽  
Dalin Zhang ◽  
Guanghui Su ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Sodium Fast Reactor

Decay Heat Characterization for the European Sodium Fast Reactor

2021 ◽  
Author(s):  
Antonio Jiménez-Carrascosa ◽  
Nuria Garcia Herranz ◽  
Jiri Krepel ◽  
Marat Margulis ◽  
Una Baker ◽  
...  
Keyword(s):  
Fast Reactor ◽  
State Of The Art ◽  
Nuclear Data ◽  
Summation Method ◽  
Heat Power ◽  
Coupled Transport ◽  
Decay Heat ◽  
Sodium Fast Reactor ◽  
Detailed Assessment ◽  
Commercial Size

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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