scholarly journals Design and Selection of Innovative Primary Circulation Pumps for GEN-IV Lead Fast Reactors

Energies ◽  
2017 ◽  
Vol 10 (12) ◽  
pp. 2079 ◽  
Author(s):  
Walter Borreani ◽  
Alessandro Alemberti ◽  
Guglielmo Lomonaco ◽  
Fabrizio Magugliani ◽  
Paolo Saracco
Keyword(s):  
Fast Reactors ◽  
Gen Iv ◽  
Selection Of

Results of a New Production of Nuclear-Grade 1.4970 ‘15-15Ti’ Stainless Steel Fuel Cladding Tubes for GEN IV Reactors

2014 ◽  
Author(s):  
Rémi Delville ◽  
Erich Stergar ◽  
Marc Verwerft
Keyword(s):  
Stainless Steel ◽  
Microstructural Analysis ◽  
Nuclear Grade ◽  
Fuel Cladding ◽  
Fast Reactors ◽  
New Production ◽  
Steel Grades ◽  
Gen Iv ◽  
Past Experiences ◽  
Cladding Material

Titanium stabilized 1.4970 ‘15-15Ti’ stainless steel cladding is the primary choice for fuel cladding of several current fast spectrum research reactor projects. The choice of cladding material is based on past experiences and the availability of material databases from similar steel grades that have proven their reliability in past sodium-cooled fast reactors programs. However the last production in Europe of nuclear-grade 15-15Ti was more than 20 years ago and it remained to be seen if the know-how to produce such steel with the strict specifications for nuclear fuel cladding was still available. Results of a new production of nuclear-grade 15-15Ti cladding tubes at Sandvik for SCK•CEN is presented in this paper. It is shown that materials properties are within the strict specifications similar to the ones used during past sodium-cooled fast reactors programs. Special attention is given to microstructural analysis of the newly produced steel which contains a large number of stabilizing Ti(C-N) precipitates known for their beneficial effect on in-pile material properties and thermal creep. Results from metallography, SEM and TEM investigations are presented.

Proposals of Improvements of RCC-MR Creep-Fatigue Rules

2007 ◽  
Author(s):  
Marie-Noe¨l Berton ◽  
Olivier Ancelet ◽  
Marie The´re`se Cabrillat ◽  
Ste´phane Chapuliot
Keyword(s):  
Stress Relaxation ◽  
Fatigue Damage ◽  
High Temperatures ◽  
Dwell Time ◽  
Damage Evaluation ◽  
Fast Reactors ◽  
Creep Fatigue ◽  
Sodium Fast Reactors ◽  
Gen Iv ◽  
Current Rule

The RCC-MR creep-fatigue rules were developed and written in the framework of studies for the first SFR (Sodium Fast Reactors). These reactors were characterized by low primary loads and moderately high temperatures. The rule thus has to be improved with the aim of decreasing its conservatisms in case of higher temperatures and/or higher pressures (for GEN IV Gas Cooled Reactors). Studies were realized to improve the rule on the following points: - the position of the temperature dwell time in the cycle : the current rule always considers that the dwell time is located at one of the extremes of the cycle, what can be very conservative in some cases, - the symmetrisation effect of the stabilized cycle, - the case where the primary loads vary during the cycle, - the primary and secondary stresses combination during the temperature dwell time for the evaluation of the stress relaxation. These works are based on viscoelastoplastic calculations of stabilized cycles and the new proposals are applied on different tests. The consequences on creep-fatigue damage evaluation can be very significant.

Selection of sodium coolant for fast reactors in the US, France and Japan

2013 ◽  
Vol 254 ◽  
pp. 194-217 ◽  
Author(s):  
Yoshihiko Sakamoto ◽  
Jean-Claude Garnier ◽  
Jacques Rouault ◽  
Christopher Grandy ◽  
Thomas Fanning ◽  
...  
Keyword(s):  
Sodium Coolant ◽  
Fast Reactors ◽  
The Us ◽  
Selection Of

scholarly journals EFFECT OF WORKING FLUID ON SELECTION OF GAS TURBINE CYCLE CONFIGURATION FOR GEN-IV NUCLEAR POWER PLANT SYSTEM

2019 ◽  
Vol 2019.27 (0) ◽  
pp. 2082
Author(s):  
Emmanuel O. Osigwe ◽  
Arnold Gad-Briggs ◽  
Pericles Pilidis ◽  
Theoklis Nikolaidis ◽  
Suresh Sampath
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Gas Turbine ◽  
Nuclear Power ◽  
Working Fluid ◽  
Plant System ◽  
Gen Iv ◽  
Gas Turbine Cycle ◽  
Selection Of

scholarly journals Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum

2018 ◽  
Vol 2018 ◽  
pp. 1-16
Author(s):  
N. Chrysanthopoulou ◽  
P. Savva ◽  
M. Varvayanni ◽  
C. Colin ◽  
C. Huot-Marchand ◽  
...  
Keyword(s):  
Energy Spectrum ◽  
Cross Section ◽  
Neutron Spectrum ◽  
Inelastic Neutron Scattering ◽  
Material Testing ◽  
Inelastic Neutron ◽  
Neutron Energy Spectrum ◽  
Reactor Safety ◽  
Gen Iv ◽  
Selection Of

The safe introduction of Generation IV (Gen IV) reactor concepts into operation will require extensive testing of their components. This must be performed under neutronic conditions representative of those expected to prevail inside the new reactor cores when in operation. In a thermal Material Testing Reactor (MTR) such neutronic conditions can be achieved by tailoring the prevailing neutron spectrum with the utilization of a device containing appropriate materials. In this work various materials are investigated as candidate components of a device that will be required in case that a thermal MTR neutron energy spectrum must be locally transformed, so as to imitate Sodium cooled Fast Reactor (SFR). Many nuclides have been examined with respect to only their neutronic behavior, providing thus a pool of neutronically appropriate materials for consideration in further investigation, such as regarding reactor safety and fabrication issues. The nuclides have been studied using the neutronics code TRIPOLI-4.8 while the reflector of the Jules Horowitz Reactor (JHR) was considered as the hosting environment of the transforming device. The results obtained suggest that elements with important inelastic neutron scattering could be chosen at a first level as being able to modify the prevailing neutron spectrum towards the desired direction. The factors which are important for an effective inelastic scatterer comprise density and inelastic microscopic cross section, as well as the energy ranges where inelastic scattering occurs. All the above factors have been separately examined in order to suggest potential device materials, able to locally produce SFR neutron spectrum imitation in a thermal MTR.

Selection of Matrices for Immobilization of Actinide Fraction of HLW

2002 ◽  
Vol 757 ◽  
Author(s):  
A. V. Ochkin ◽  
S. V. Stefanovsky ◽  
S. I. Rovny
Keyword(s):  
Storage Time ◽  
Fission Products ◽  
Alpha Activity ◽  
Separation Method ◽  
Fast Reactors ◽  
Long Term Storage ◽  
Perovskite Ceramics ◽  
Term Storage ◽  
Selection Of

ABSTRACTHLW after the separation of U, Pu and Np contains two major radionuclide groups: fission products and TRU elements. The later ones are the most dangerous and should be separated in the special actinide fraction. This process has been realized at PA “Mayak”.The composition of the actinide fraction depends on a separation method:A. Radionuclides of Am and Cm with minor amounts of U, Np and Pu.B. Radionuclides of Am and Cm with minor amounts of U, Np and Pu and also REEs.C. Radionuclides of Am and Cm with minor amounts of U, Np and Pu and also REEs and perhaps some amount of Zr.The fraction with composition A can be burned off in fast reactors whereas the fractions with compositions B and C should be immobilized in stable matrices. Alpha-Activity of actinide fraction is subsequently determined by 244Cm, 241Am, 244Am, 239Pu and 242Pu during a long-term storage. The storage time depends on conditions and can reach several hundreds of thousands years. The main requirements to matrices are chemical and radiation resistances. The fraction with composition B can be incorporated in perovskite ceramics whereas in case of composition C the additional zirconolite and/or pyrochlore phases are necessary.

Knowledge-Based Information Resource Management System for Materials of Fast Reactors

2009 ◽  
Author(s):  
Hsuan-Tsung Sean Hsieh ◽  
Ning Li ◽  
Yitung Chen ◽  
Kenny Kwan ◽  
Jen-Yuan Huang ◽  
...  
Keyword(s):  
Knowledge Discovery ◽  
Gap Analysis ◽  
Technology Development ◽  
Advanced Materials ◽  
Data Sets ◽  
Distributed Data ◽  
Data Generation ◽  
Fast Reactors ◽  
Web Based ◽  
Gen Iv

In the development of advanced fast reactors, materials and coolant/material interactions pose a critical barrier for higher temperature and longer core life designs. For advanced burner reactors (sodium cooled), experience has shown that the qualified structural materials and fuel cladding severely limits the economic performance. In other liquid metal cooled reactor concepts, advanced materials and better understanding and control of coolant and materials interactions are necessary for realizing the potentials. Researches from universities, national laboratories and related industrial participants have been continuously generating invaluable data and knowledge about materials and their interactions with coolants in the past few decades. Under the consideration of cost and time constraints, the paradigm of designing and implementing a successful Gen IV Nuclear Energy Systems can be shifted and updated via the integration of information and internet technologies. Such efforts can be better visualized by implementing collective (centralized or distributed) data storages to serve the community with organized material data sets. Material property data provided by MatWeb.com and the ongoing development of web-based GEN IV material handbook are few examples. From system design perspective, sodium-cooled fast reactor (SFR) proposed in the GEN IV system have been significantly developed. According to the GEN IV ten-year program plan, current R&D work will be pointed to demonstration of the design and safety characteristics, and design optimization. All of those activities follow the path of data generation, analysis, knowledge discovery and finally decision making and implementation. We are proposing to create a modularized web-based information system with models to systematically catalog existing data and guide the new development and testing to acquire new data. Technically speaking, information retrieval and knowledge discovery tools will be implemented for researchers with both information lookup options from material database and technology/development gap analysis from intelligent agent and reporting components. The goal of the system is not only to provide another database, but also to create a sharable and expandable platform-free, location-free online system for research institutes and industrial partners.

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