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.

Nuclear Partition

2018 ◽  
pp. 33-90
Author(s):  
Chaitanya Ravi
Keyword(s):  
Social Construction ◽  
Science And Technology Studies ◽  
Organizational Infrastructure ◽  
The Social ◽  
Collective Actors ◽  
The Status ◽  
Indian State ◽  
Theory Section ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

The second chapter begins with an explanation of the origins, evolution, and organizational infrastructure of the Indian nuclear programme. Three Science and Technology Studies (STS) case studies deploying the Social Construction of Technology (SCOT) approach are introduced in the theory section and their combined insights are used to organize various individual and collective actors in India based on their initial reactions to the nuclear deal. The chapter then focuses specifically on the debate between two powerful bureaucracies (Department of Atomic Energy [DAE] and Ministry of External Affairs [MEA] within the Indian state over the civilian-military proportions of the separation plan and the status of the fast breeder reactors). The MEA’s generalist vision and the DAE’s narrower departmental vision are observed in the form of two contending separation plans with different civil-military facility balances and rival safeguarded versus unsafeguarded statuses of the fast breeder reactor. The DAE’s tactics to win the debate are elucidated.

scholarly journals A NEW NUCLEAR DENSITY GAUGE TO MEASURE DIRECTLY HIGH TURBIDITIES IN MUDDY AREAS

1984 ◽  
Vol 1 (19) ◽  
pp. 212 ◽  
Author(s):  
A. Caillot ◽  
G. Meyer ◽  
D. Chambellan ◽  
J.C. Tanguy
Keyword(s):  
Atomic Energy Commission ◽  
Atomic Energy ◽  
Nuclear Density ◽  
Dynamic Measurements ◽  
New Developments ◽  
Precise Adjustment ◽  
The Status ◽  
Nuclear Density Gauge ◽  
Rational Organization ◽  
Maintenance Dredging

A better knowledge of the characteristics of muddy areas, in access fairways and port basins, and of the behaviour of ships during their crossing, presents the double interest of enhancing the navigation possibilities, through a more precise adjustment of the ship draught to the status of the bottoms, and permiting a more rational organization of the maintenance dredging campaigns. Considerable savings will be obtained through the development of such knowledges for harbours management. These improvements imply the use of measuring equipments which must be handy, sturdy, reliable and which give accurate measurements. The JTD3 gauge presented by the Radioisotopes Applications Service of the French Atomic Energy Commission is an important step in the development of such measuring equipments. It is now in running order, and commercially available, after thorough test campaigns, undertaken during many months in different french harbours. New developments are already engaged, namely through the design of a turbidity gauge able to make dynamic measurements.

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.

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.

Radiological safety and assessment of the performance of X-ray systems in veterinary facilities

2020 ◽  
Author(s):  
S. Economides ◽  
C.J. Hourdakis ◽  
C. Pafilis ◽  
G. Simantirakis ◽  
P. Tritakis ◽  
...  
Keyword(s):  
Decision Making ◽  
Radiation Protection ◽  
Atomic Energy Commission ◽  
Atomic Energy ◽  
Regulatory Control ◽  
Continuous Training ◽  
X Ray ◽  
The Public ◽  
Radiological Safety ◽  
High Level

This paper concerns an analysis regarding the performance of X-ray equipment as well as the radiological safety in veterinary facilities. Data were collected from 380 X-ray veterinary facilities countrywide during the on-site regulatory inspections carried out by the Greek Atomic Energy Commission. The analysis of the results shows that the majority of the veterinary radiographic systems perform within the acceptable limits; moreover, the design and shielding of X-ray rooms as well as the applied procedures ensure a high level of radiological safety for the practitioners, operators and the members of the public. An issue that requires specific attention in the optimization process for the proper implementation of veterinary radiology practices in terms of radiological safety is the continuous training of the personnel. The above findings and the regulatory experience gained were valuable decision-making elements regarding the type of the regulatory control of veterinary radiology practices in the new radiation protection framework.

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