Speaker
Description
The SVBR-100 reactor facility with a fast neutron reactor, an integral layout of the primary circuit and a lead-bismuth coolant in the primary circuit is being developed as one of the main components of serial NPPs of modular design with an average power from 100 to 600 MW (e).
The main design provisions of the SVBR-100 reactor facility,presented in the paper,are aimed at simplifying the design of reactor facility equipment and systems, using the inherent safety characteristics and passive systems to increase the resistance of the reactor facility to potential hazards. Due to the developed properties of internal self-protection, the number and complexity of safety systems has been significantly reduced in comparison with traditional reactor facilities. Key technical solutions used in reactor plant designs are based on mastered production materials and technologies.
The most important technical characteristics of the reactor facility are presented in Table below.
Main technical characteristics of reactor facility SVBR-100
Characteristic Value
Thermal power, MW 280
Pressure of generated saturated steam, MPa 7.0
Steam capacity, t/h 580
Coolant temperature at core inlets/outlets, °C 340/490
Fuel OU2
Average fuel enrichment for U-235, % 16.7
Maximum fuel enrichment for U-235, % less than 20
Core campaign, thousand effective hours 50
Time interval between refueling, years 6-7
Reactor dimensions: diameter/height, m 4.53/7.86
A significant amount of R&D has been carried out to substantiate the technical design of the reactor facility. The most important results and the main directions of activities for completing the justifications are presented in the paper.
In-depth technical and economic researches carried out on the basis of design documents demonstrate the competitiveness of the product being created.
| Country OR International Organization | Russian Federation |
|---|---|
| Email address | A.Dedul@svbr.org |
| Confirm that the work is original and has not been published anywhere else | YES |
