LOCA Analysis of Super Fast Reactor
スポンサーリンク
概要
- 論文の詳細を見る
This paper describes loss of coolant accident (LOCA) analyses of the Supercritical-pressure Water-Cooled Fast Reactor (Super Fast Reactor). The features of the Super Fast Reactor are high power density and downward flow cooled fuel channels for the improvement of the economic potential of the Super Fast Reactor with high outlet steam temperature. The LOCA induces large pressure and coolant density change in the core. This change influences the flow distribution among the downward flow parallel channels. It will affect the safety of the Super Fast Reactor. LOCA analysis of Super Fast Reactor is important to understand the safety features of the Super Fast Reactor. Keeping the flow rate in the core is important for the safety of the Super Fast Reactor. In LOCA, it is difficult to maintain an adequate flow rate due to the once-through coolant cycle and the downward flow cooled fuel assemblies. Therefore, the early actuation of the Automatic Depressurization System (ADS) and reduction of the maximum linear heat generation rates of the downward flow seed fuel assemblies and Low-Pressure Core Spray (LPCS) system are necessary for the Super Fast Reactor to cool the core under LOCA. Analysis results show that the Super Fast Reactor can satisfy the safety criteria with these systems.
- 一般社団法人 日本原子力学会の論文
著者
-
Oka Yoshiaki
Nuclear Engineering Research Laboratory Graduate School Of Engineering The University Of Tokyo
-
Ishiwatari Yuki
Department Of Nuclear Engineering And Management The University Of Tokyo
-
IKEJIRI Satoshi
Nuclear Professional School, The University of Tokyo
-
HAN Chi
Nuclear Professional School, The University of Tokyo
関連論文
- 特集座談会 原子力教育に新風を吹き込めるか?--東京大学・原子力グローバルCOE「世界を先導する原子力教育研究イニシアチブ」に取り組んで見えてきたもの
- 原子力学会会員は技術士資格を今すぐ取ろう
- グローバルCOEプログラム「世界を先導する原子力教育研究イニシアチブ」
- 学会はどこまで利用できるか? : 相互研さんやシナジーの「場」としての可能性を問う
- 3521 粒子法による原子炉内の混相流に関する詳細解析(S49-2 流動,原子炉用機器(1),S49 原子炉システムおよびその要素技術)
- 革新的な原子炉設計とロードマップ (特集 第四世代の原子力システムに向けて)
- Numerical Analyses of Flashing Jet Structure and Droplet Size Characteristics
- Numerical and Theoretical Investigation of Effect of Density Ratio on the Critical Weber Number of Droplet Breakup
- ICONE11-36029 DROPLET BREAKUP UNDER IMPULSIVE ACCELERATION USING MOVING PARTICLE SEMI-IMPLICIT METHOD
- 粒子法によるジェット分散挙動の数値解析
- Numerical Analysis of Jet Injection Behavior for Fuel-Coolant Interaction using Particle Method
- 創立50周年を迎えて
- 行動する学会をめざして
- 「サステナビリティと原子力教育研究」をテーマに講演と討論東京大学原子力グローバルCOE拠点創立記念 : 第2回国際シンポジウム
- 計算科学技術概観, 連続体のシミュレーション手法と適用例(その1)
- 米国原子力学会2004年冬季大会
- 第16回環太平洋原子力会議から
- Measurements of Neutron Capture Cross Section of ^Np for Fast Neutrons
- ATWS Characteristics of Super LWR with/without Alternative Action
- LOCA Analysis of Super LWR
- Fuel and Core Design of Super Light Water Reactor with Low Leakage Fuel Loading Pattern
- Development of Statistical Thermal Design Procedure to Evaluate Engineering Uncertainty of Super LWR
- Safety of Super LWR, (II) : Safety Analysis at Supercritical Pressure
- Safety of Super LWR, (I) : Safety System Design
- Thermal and Stability Considerations of Super LWR during Sliding Pressure Startup
- Evaluation of the Energy Conversion Ratio of Vapor Explosions for the Assessment of Nuclear Reactor Safety
- Three-dimensional numerical simulation of droplet deposition
- A Particle-mesh Method for Incompressible Multiphase Flows
- The Role of Fragmentation Mechanism in Large-Scale Vapor Explosions(International Conferences on Power and Energy System)
- ICONE11-36047 The Role of Fragmentation Mechanism in Large-scale Vapor Explosions
- Investigation on Energetics of Ex-Vessel Vapor Explosion Based on Spontaneous Nucleation Fragmentation
- HMPS(Hamiltonian Moving Particle Semi-implicit)法の開発(第2報)シンプレクティックスキームの適用
- HMPS(Hamiltonian Moving Particle Semi-implicit)法の開発(第1報)運動方程式の導出
- 1031 Hamiltonian に基づく非圧縮流れ粒子法の開発
- Improvements of Feedwater Controller for the Super Fast Reactor
- Supercritical-pressure, Once-through Cycle Light Water Cooled Reactor Concept
- A Linear Stability Analysis of Supercritical Water Reactors, (II) : Coupled Neutronic Thermal-Hydraulic Stability
- A Linear Stability Analysis of Supercritical Water Reactors, (I) : Thermal-Hydraulic Stability
- Startup Thermal Analysis of a High-Temperature Supercritical-Pressure Light Water Reactor
- Numerical Analysis of Jet Breakup Behavior Using Particle Method
- Numerical Simulation of Liquid Drop Deposition in Annular-Mist Flow Regime of Boiling Water Reactor
- Core Design of a Direct-Cycle, Supercritical-Pressure, Light Water Reactor with Double Tube Water Rods
- Flow-Induced Accident and Transient Analyses of a Direct-Cycle, Light-Water-Cooled, Fast Breeder Reactor Operating at Supercritical Pressure
- Three-dimensional Core Design of High Temperature Supercritical-Pressure Light Water Reactor with Neutronic and Thermal-Hydraulic Coupling
- Control of a High Temperature Supercritical Pressure Light Water Cooled and Moderated Reactor with Water Rods
- Numerical Analysis of Droplet Breakup Behavior using Particle Method
- Breeding Ratio Analysis of a Fast Reactor Cooled by Supercritical Light Water
- 原子力教育研究のフロンティア構築を目指して (特集 東大グローバルCOEプログラム 世界を先導する原子力教育研究イニシアチブ)
- Fuel, Core Design and Subchannel Analysis of a Superfast Reactor
- Simulation of a Single Bubble Rising with Hybrid Particle-Mesh Method
- LOCA Analysis of Super Fast Reactor
- MPS法による弾性構造体の動的解析
- A CONCEPTUAL DESIGN OF LIB FUSION REACTOR : UTLIF (2)
- LOCA Analysis of Super Fast Reactor
- Numerical and Theoretical Investigation of Effect of Density Ratio on the Critical Weber Number of Droplet Breakup
- Control of a High Temperature Supercritical Pressure Light Water Cooled and Moderated Reactor with Water Rods
- Neutron streaming through narrow and long annulus.
- Simulation of multigroup X-ray, alpha-particle and neutron transport in ion beam driven ICF target.
- Effect of Zirconium-Hydride Layers on Reducing Coolant Void Reactivity of Steam Cooled Fast Breeder Reactors.
- Some relations of neutronic noise with fluctuation of inlet coolant temperature and vibration of a control rod obtained by simultaneous measurements at KUR.
- A Direct-Cycle, Supercritical-Water-Cooled Fast Breeder Reactor.
- Development of three-dimensional space dependent kinetics code IBIS and analysis of transient behavior of LMFBR cores.
- Fast neutron spectra transmitted through iron and sodium slabs.
- Concept and nuclear performance of direct-enrichment fusion breeder blanket using UO2 powder.
- Measurement and analysis of neutron leakage spectrum from nickel sphere for 14 MeV neutron source.
- Concept and nuclear performance of power-producing fast fission blankets for fusion-fission hybrid reactors using equilibrium fissile fuel.