Fast Reactor System Design

2017 ◽  
Keyword(s):  
System Design ◽  
Fast Reactor ◽  
Reactor System

Development of Advanced Loop-Type Fast Reactor in Japan: Progress of Design Study Based on Preliminary Assessment Results

2010 ◽  
Author(s):  
Yoshihiko Sakamoto ◽  
Shoji Kotake ◽  
Kazumi Aoto ◽  
Mikio Toda
Keyword(s):  
System Design ◽  
Fast Reactor ◽  
Structural Integrity ◽  
Technology Development ◽  
Development Project ◽  
Reactor Vessel ◽  
Reactor System ◽  
Preliminary Assessment ◽  
Design Study ◽  
Seismic Force

The Japan sodium-cooled fast reactor (JSFR) is an advanced loop-type reactor concept which is investigated in the Fast Reactor Cycle Technology Development project in Japan. This paper describes some important progress on the JSFR design study and R&D discussed in a preliminary assessment for the first milestone of this project. As for the reactor system design, structural integrity against both thermal stress and seismic force was investigated. Then, the specification of the reactor vessel was established. Also, investigation of design options to extend a design margin against seismic force has been suggested. Regarding thermal hydraulics issues in the reactor vessel, design measures against cover gas entrainment and vortex cavitations have been introduced to the reactor system design based on R&D results. Further investigation is in progress for design optimization or improvement of preventive effect. The hot-leg piping design of primary cooling circuit was also established taking “Type-IV” damage into account.

scholarly journals Development of Advanced Radiation Resistant ODS Steel for Fast Reactor System Applications

2015 ◽  
Vol 03 (03) ◽  
pp. 125-128 ◽  
Author(s):  
Tae Kyu Kim ◽  
Sanghoon Noh ◽  
Suk Hoon Kang ◽  
Hyun Ju Jin ◽  
Ga Eon Kim
Keyword(s):  
Fast Reactor ◽  
Reactor System ◽  
Ods Steel ◽  
Radiation Resistant

CFD Analysis Applications in BWR Reactor System Design

2010 ◽  
pp. 199-221
Author(s):  
Yuichiro Yoshimoto ◽  
Shiro Takahashi
Keyword(s):  
System Design ◽  
Reactor System ◽  
Cfd Analysis

System Design and Analysis of a 900-MW(thermal) Lead-Cooled Fast Reactor

2010 ◽  
Vol 170 (1) ◽  
pp. 148-158
Author(s):  
Sang Ji Kim ◽  
Yonghee Kim ◽  
Sergi Hong ◽  
Chung Ho Cho ◽  
Jae-Hyuk Eoh ◽  
...  
Keyword(s):  
System Design ◽  
Fast Reactor

scholarly journals Scram and nonlinear reactor system seismic analysis for a liquid metal fast reactor

1976 ◽  
Vol 38 (3) ◽  
pp. 555-566 ◽  
Author(s):  
A. Morrone ◽  
A.N. Nahavandi ◽  
W.G. Brussalis
Keyword(s):  
Liquid Metal ◽  
Fast Reactor ◽  
Seismic Analysis ◽  
Reactor System

Allegro: The European Gas Fast Reactor Demonstrator Project

2009 ◽  
Author(s):  
Christian Poette ◽  
Vale´rie Brun-Magaud ◽  
Franck Morin ◽  
Jean-Franc¸ois Pignatel ◽  
Richard Stainsby ◽  
...  
Keyword(s):  
High Temperature ◽  
Fast Reactor ◽  
Heat Removal ◽  
Reactor System ◽  
Large Temperature ◽  
The Core ◽  
Intermediate Heat Exchanger ◽  
Current Design ◽  
Ceramic Fuel ◽  
High Temperature Components

In the Gas Fast Reactor development plan, ALLEGRO is the first necessary step towards the electricity generating prototype GFR. The ALLEGRO start of operation is planned by 2020. This needs to define all design options in 2010 and to start detailed design studies in 2013. ALLEGRO is a low power Gas Cooled Fast Reactor studied in the European framework. It is a loop type, non electricity generating reactor. Its power is about 80 MW. Several objectives are assigned to ALLEGRO. At first, it will demonstrate the viability of the GFR reactor system, no reactor of this type having been built in the past. Most of the GFR architecture, materials and components features are considered at reduced scale in ALLEGRO, excluding the energy conversion system. ALLEGRO will rely on the same safety options as the reactor system. In addition, the ALLEGRO core will allow the progressive qualification of the GFR ceramic fuel, with the possibility to load some ceramic carbide or nitride sub-assemblies in a first MOX core, with SiC/SiCf cladding and wrappers. When such unit test will be considered convincing enough, the diagrid and circuits are designed to accept full high temperature ceramic cores. The core neutrons can also be used to irradiate structural materials with fast neutron spectrum and in a large temperature range. The core can also include innovative irradiation fuel devices (samples or full bundles) for other reactor systems. Finally, branches on the main intermediate heat exchanger will allow the testing and validation of high temperature components and processes. The pre-conceptual design of ALLEGRO is shared between European partners through the GCFR 6th R&D Framework Program. After recalling the role of the European partners in the different design and safety tasks, the paper will give an overview of the current design with recent progresses in various areas like: • Core design and neutron performances, • The design of experimental advanced ceramic GFR fuel sub-assemblies included in several locations of the MOX core, • Fuel handling principles and solutions, • System design and global reactor architecture which is largely influenced by the Decay Heat Removal strategy (DHR) for depressurized accidents.

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