Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
スポンサーリンク
概要
- 論文の詳細を見る
Design and safety aspects of long-life small safe fast reactors using liquid lead or leadbismuth coolant with metallic or nitride fuel are discussed. Neutronic analyses are performedto investigate the effect of core height to diameter ratio (H/D) on design performance of theproposed reactors. All reactors are subjected to the constraint of 12 years operation withoutrefueling and shuffling with constant 150MWt reactor power and also to the requirement of maximum excess reactivity during burnup to be less than 0.1%Δk. The results show that the pancake design with H/D of -2/3 gives the most negative coolant void coefficient under the requirements for excess reactivity. Modified designs with the central region axially fulfilled with fertile material are proposed to improve the coolant void coefficient. Ther al-hydraulicanalysis results show the possibility to operate the reactors up to the end of life without changing their orifice pattern, necessary pumping power for the proposed design smaller than the conventional large sodium cooled FBR, and the natural circulation contribution of 25-40% at the normal operating condition. The reactivity feedback coefficients are also estimated andappeared to be negative for all the components including the coolant density coefficient.
- 社団法人 日本原子力学会の論文
- 1995-09-25
著者
関連論文
- Breeding Capability and Void Reactivity Analysis of Heavy-Water-Cooled Thorium Reactor
- ICONE11-36126 Examination of applicability of IK method in the negative reactivity measurements
- ICONE11-36061 APPLICATION OF CANDLE BURNUP TO BLOCK-TYPE HIGH TEMPERATURE GAS COOLED REACTOR
- A New Estimation Method for Nuclide Number Densities in Equilibrium Cycle
- Radioactive Waste Transmutation and Safety Potentials of the Lead Cooled Fast Reactor in the Equilibrium State
- Comparison of the Burnup Characteristics and Radiotoxicity Hazards of Rock-like Oxide Fuel with Different Types of Additives
- Application of Monte Carlo Method to Solve the Neutron Kinetics Equation for a Subcritical Assembly
- Measurement of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of ^Bi
- Feasible Region of Design Parameters for Water Cooled Thorium Breeder Reactor
- Effects of Fuel and Coolant Temperatures and Neutron Fluence on CANDLE Burnup Calculation
- Sensitivities of Some Characteristics of Nuclear Equilibrium State to One-Group Constants
- Transport Equivalent Diffusion Constants for Reflector Region in PWRs
- ICONE11-36045 Removal of Polonium Contamination by Lead-Bismuth Eutectic in Nuclear Systems
- Calculational Method of One-Group Nuclear Constants in Nuclear Equilibrium State
- Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particles
- Exact Error Estimation for Solutions of Nuclide Chain Equations
- Characteristics of Several Equilibrium Fuel Cycles of PWR
- Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
- Fast neutron spectrum in lithium fluoride pile with D-T neutron source.
- New method to analyze equilibrium cycle of pebble-bed reactors.
- Scalar fast neutron spectra in graphite-reflected lithium fluoride pile with D-T neutron source.
- Burn-off and Production of CO and CO2 in the Oxidation of Nuclear Reactor-Grade Graphites in a Flow System.