Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

2000 ◽  
Vol 123 (1) ◽  
pp. 49-57 ◽  
Author(s):  
Tai Asayama ◽  
Yasuhiro Abe ◽  
Noriko Miyaji ◽  
Mamoru Koi ◽  
Tomohiro Furukawa ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Environmental Effects ◽  
Structural Design ◽  
Neutron Fluence ◽  
Evaluation Procedure ◽  
Fast Breeder Reactor ◽  
Irradiation Effects ◽  
Creep Life ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

In the structural design of fast breeder reactors, irradiation effects and sodium environmental effects on structural materials have to be taken into account. In this paper, firstly, an evaluation procedure for irradiation effects on the mechanical properties of 316FR (FBR Grade 316 stainless steel), which is a newly developed stainless steel for the Japanese demonstration fast breeder reactor, is proposed. The procedure gives a limit of accumulated fast neutron fluence E>0.1 MeV as a function of temperature, so that the minimum tensile fracture elongation of 10 percent, which is the threshold for material to stay ductile, is maintained. Furthermore, the procedure determined a creep life reduction factor and a creep rate increase factor as a function of accumulated thermal neutron fluence E<0.4 eV, within the limitation of the accumulated fast neutron fluence, to account for the creep life reduction and the increase of creep rate due to irradiation. Secondly, an evaluation procedure for sodium environmental effects on the integrity of 316FR and modified 9Cr-1Mo steel was proposed. It gave a corrosion allowance as a function of temperature, oxygen content, and service time, based on corrosion tests. It determined that no correction factors that correspond to sodium environment on design allowable stresses, etc., are needed, because no adverse effects of sodium on the mechanical properties of 316FR and modified 9Cr-1Mo steel were to be expected in the service conditions of FBRs. Both the procedures have been incorporated into the Japanese Elevated Temperature Structural Design Guide for Demonstration Fast Breeder Reactor.

An Integrated Approach for the Structural Reliability Evaluation of Fast Breeder Reactor Components

2004 ◽  
Author(s):  
Tai Asayama ◽  
Nobuchika Kawasaki ◽  
Masaki Morishita
Keyword(s):  
Structural Design ◽  
Structural Reliability ◽  
Integrated Approach ◽  
Linear Formulation ◽  
Fast Breeder Reactor ◽  
Trial And Error ◽  
Error Type ◽  
Design Variables ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

For the improvement of structural design of fast breeder reactors, a new method for the optimization of structural reliability is proposed. This method approximates failure probability of a component by a linear formulation of various design variables. The formulation is obtained by a theoretical calculation extended by numerical considerations based on Monte Carlo simulation. This method allows a designer to optimize reliability without trial-and-error type calculations.

Irradiation effects of boron carbide used as control rod elements in fast breeder reactors

1978 ◽  
Vol 74 (1) ◽  
pp. 114-122 ◽  
Author(s):  
Tadashi Inoue ◽  
Takeo Onchi ◽  
Hiroaki Kôyama ◽  
Hiroshige Suzuki
Keyword(s):  
Boron Carbide ◽  
Irradiation Effects ◽  
Control Rod ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

Development of Material and Structural Reliability Evaluation System MSS-REAL

2006 ◽  
Author(s):  
Tai Asayama ◽  
Takehiko Kato ◽  
Masaki Morishita
Keyword(s):  
Life Cycle ◽  
Structural Design ◽  
Evaluation System ◽  
Structural Reliability ◽  
Evaluation Method ◽  
Reliability Evaluation ◽  
The Other ◽  
Material Strength ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

For the development of the System Based Code, which was proposed by Asada and intends to optimize structural design of nuclear components by enabling margin exchange between various technical options, a tool for life cycle structural reliability evaluation method is necessary. For this purpose, the authors are developing a material strength and structural reliability evaluation system MSS-REAL. The system is primarily for fast breeder reactors but its methodologies can also be applied to the other types of reactors. This paper summarizes the features of the MSS-REAL system with examples and also describes a future development plan.

Balancing material selection and inspection requirements in structural design of fast breeder reactors based on “System Based Code” concept

2008 ◽  
Vol 238 (2) ◽  
pp. 417-422 ◽  
Author(s):  
Tai Asayama ◽  
Nobuchika Kawasaki ◽  
Masaki Morishita ◽  
Hiroshi Shibamoto ◽  
Kazuhiko Inoue
Keyword(s):  
Structural Design ◽  
Material Selection ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

scholarly journals A Consideration on Limits of Cold Working in Nuclear Construction

1975 ◽  
Vol 97 (2) ◽  
pp. 162-171 ◽  
Author(s):  
R. A. Moen ◽  
G. V. Smith
Keyword(s):  
Mechanical Properties ◽  
Elevated Temperature ◽  
Cold Working ◽  
Cold Work ◽  
Time Dependent ◽  
Subsequent Performance ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Materials Used ◽  
Work Level

Cold working of metals affects the mechanical properties of those metals. These effects are particularly important in the design, analysis and subsequent performance of materials used in elevated temperature nuclear construction. This paper provides an assessment of the effects of cold working on the time independent and time dependent mechanical properties of the materials most commonly encountered in liquid metal fast breeder reactors. The paper suggests specific reductions, as a function of time, temperature and cold work level, for those properties adversely affected. The final objective of this paper is to provide an assessment of the manner in which the Code now addresses fabrication effects and how it might make those assessments in the future.

The economics of fast breeder reactors

1990 ◽  
Vol 331 (1619) ◽  
pp. 435-443 ◽  
Keyword(s):  
Atomic Energy Commission ◽  
Atomic Energy ◽  
Reactor System ◽  
Economic Potential ◽  
Fast Breeder Reactor ◽  
The Status ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Economic Considerations

The overall status of the fast breeder reactor (FBR) system is periodically reviewed in France. In 1983, a report was prepared on the status and prospects of the FBR system at the request of the then Minister of Industry. Five years later, Electricite de France (EdF) and the French Atomic Energy Commission (CEA) jointly updated this report. The FBR reactor system economic considerations mentioned here are taken from the work performed in 1987—88 for this updating. The position in 1983 is reviewed to highlight concrete developments. Developments that have occurred since then are presented, along with the prospects that today enable us to define better the technical and economic potential of the FBR system. In conclusion, the effects of these findings on desirable directions are discussed, in particular with regard to European FBR cooperation.

Pressureless Sintering of B4C Neutron Absorbing Material with Nano-Sized Rare-Earth Compounds Addition

2012 ◽  
Vol 602-604 ◽  
pp. 503-507
Author(s):  
Ru Bin Wei ◽  
Yu Jun Zhang ◽  
Hong Yu Gong ◽  
Xiao Jun Liu ◽  
Ya Zhen Jiang ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Rare Earth ◽  
Boron Carbide ◽  
Pressureless Sintering ◽  
Rare Earth Compounds ◽  
Neutron Absorber ◽  
Absorbing Material ◽  
Fast Breeder Reactors ◽  
Dysprosium Titanate ◽  
Breeder Reactors

The processing of boron carbide by pressureless sintering with nano-sized rare-earth compounds additives to obtain dense pellets for use as neutron absorber in fast breeder reactors is investigated. The effect of dysprosium aluminum garnet (DAG) and dysprosium titanate nanopowders on density and mechanical properties was studied. The addition of DAG and dysprosium titanate nanopowders was found to be beneficial in the densification of B4C powders. B4C with 5 wt. % of DAG or dysprosium titanate nanopowders, exhibiting bulk density of 2.14g/cm3 and 2.35 g/cm3, could be prepared by pressureless heating at 2120°C and 2160°C.

Microstructure Refinement Effect on EUROFER 97 Steel for Nuclear Fusion Application

2021 ◽  
Vol 1016 ◽  
pp. 1392-1397
Author(s):  
Giulia Stornelli ◽  
Roberto Montanari ◽  
Claudio Testani ◽  
Luciano Pilloni ◽  
Giuseppe Napoli ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Pilot Scale ◽  
Detailed Knowledge ◽  
Mechanical Processing ◽  
Process Optimisation ◽  
First Wall ◽  
High Radiation ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Eurofer 97

In Europe EUROFER 97 has been recognised as reference steel for the nuclear costructions under high radiation density for first wall of a fast breeder reactors as well as in other high stressed primary structures such as the divertors, blanklet and vessels. Following to this a EUROFER 97 detailed knowledge of the microstructure evolution after thermo-mechanical processing is required, because the material mechanical properties are interesting also for innovative solar plants, i.e. NEXTOWER project. A detailed knowledge of process optimisation is mandatory because EUROFER 97 steel mechanical properties and microstruture are heavily influenced and improved (and easily affeted) by thermomechanical treatments. In this paper the effect of thermo-mechanical parameters on the grain refinement of EUROFER 97 has been investigated by cold rolling and heat treatment on pilot scale.

Radiation Damage Studies with the HVEM

1972 ◽  
Vol 30 ◽  
pp. 680-681
Author(s):  
J. J. Laidler ◽  
B. Mastel
Keyword(s):  
Radiation Damage ◽  
Stainless Steels ◽  
Volume Expansion ◽  
Austenitic Stainless Steels ◽  
Test Facility ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Under Construction ◽  
Development Laboratory ◽  
Insight Into

One of the major materials problems encountered in the development of fast breeder reactors for commercial power generation is the phenomenon of swelling in core structural components and fuel cladding. This volume expansion, which is due to the retention of lattice vacancies by agglomeration into large polyhedral clusters (voids), may amount to ten percent or greater at goal fluences in some austenitic stainless steels. From a design standpoint, this is an undesirable situation, and it is necessary to obtain experimental confirmation that such excessive volume expansion will not occur in materials selected for core applications in the Fast Flux Test Facility, the prototypic LMFBR now under construction at the Hanford Engineering Development Laboratory (HEDL). The HEDL JEM-1000 1 MeV electron microscope is being used to provide an insight into trends of radiation damage accumulation in stainless steels, since it is possible to produce atom displacements at an accelerated rate with 1 MeV electrons, while the specimen is under continuous observation.

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