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Liqued Metal Coolants for Fast Reactors Cooled by Sodium, Lead, and Lead-Bismuth Eutectic

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IAEA Nuclear Energy Series No. NP-T-1.6, Vienna, IAEA, 2012. — 95p.
This publication provides a comprehensive summary of the status of liquid coolant technology development for fast reactors with regard to basic data, main technological challenges and the various fast reactor concepts and designs that are being investigated, with a special emphasis on the choice of coolant. present report summarizes the state of the art in liquid metal technology development for fast reactors.
This report takes mainly, but not solely, into account Russian experience, activities and references.
Contents
Introduction
Short History Of Nuclear Power Development Physical And Chemical Properties Of Coolants (Sodium, Lead And Lead-Bismuth Alloy)
Liquid Metal Development (Short History)
Physical Properties
Chemical Properties
Chemical Properties Of Sodium
Chemical Properties Of Lead
Solubility Of Chemical Elements In Molten Lead-Bismuth Alloy
Comparison Of Different Sodium And Lead Coolant Technologies
Background
Sodium Technology
Impurity Sources
Purification Of Sodium And Cover Gas
Control Of Impurities Content In The Coolant And Cover Gas
Corrosion Processes In Sodium
Lead And Lead-Bismuth Technology
Basic Issues Of Technology
Impurity Sources
Cleaning From Slag
Corrosion Processes In Lead
Possibility Of Application Of Lead-Bismuth Technology Data To Lead Technology
Conclusion
Thermohydraulics Of Reactor Core
Hydrodynamics
Heat Transfer
Conclusions
Coolant Radioactivity
Sodium Radioactivity
Cleaning Caesium Radionuclide From Sodium
Lead And Lead-Bismuth Radioactivity
Conclusions
Liquid Metal Cooled Fast Reactor Technology Development
Introduction
Objectives And Challenges For The Development Of Advanced Liquid Metal Cooled Fast Reactor
Features Of Liquid Metal Cooled Fast Reactors
Physics
Economics And Experience
Conclusion
Modular Lead-Bismuth Cooled Small Size Fast Reactors
Introduction
Experience And Opportunity To Use Lead-Bismuth Eutectic Alloy As A Fast Reactors’ Coolant
Brief Description Of Experience With Lead-Bismuth Eutectic Applications
Reactor Installation SVBR-75/100
Basic Parameters Of SVBR-75/100
Description Of SVBR-75/100
Arrangement Of SVBR-75/100 Equipment
Primary Circuit Circulation Scheme
Reactor Core
Steam Generator Module
Main Circulation Pump (MCP)
In-Vessel Structures
Shielding Plug
Coolant Technology
Refueling And Storage Of Spent Nuclear Fuel
Basic Concepts Of The Nuclear Power Plant Based On SVBR-75/100
Approach
SVBR-75/100 Inherent Safety
Modular Structure Of The Nuclear Power Plant Nuclear Steam-Supplying System
SVBR-75/100 Improvement Potential
Use Of Different Kinds Of Fuel And Fuel Cycles
Handling The Radioactive Waste
Proliferation Resistance
Multi-Purpose Application Of SVBR-75/100
Opportunity To Accelerate The Pace Of Nuclear Power Development With Use Of The Proposed Nuclear Power Technology
Commercialization Concept
Conclusions
Liquid Lead Cooled Fast Reactors
The Lead Cooled Fast Reactor Concept
Nuclear Fuel Cycle Concept
Brest Concept
Lead Circulation Arrangement
Brest-1200
References

Language: English
Commentary: 1168224
Tags: Топливно-энергетический комплекс;Ядерная и термоядерная энергетика