Effect of Zirconium-Hydride Layers on Reducing Coolant Void Reactivity of Steam Cooled Fast Breeder Reactors.
スポンサーリンク
概要
- 論文の詳細を見る
The introduction of zirconium-hydride (ZrH<SUB>1.7</SUB>) layer between the seed and blanket is very effective in reducing the coolant-void reactivity of steam-cooled FBR. The void reactivity reduction is attributed to the rapid increase of neutron absorption and to the decrease of neutron production in the blanket due to the moderation through the layer. The reason is that the neutron multiplication factor decreases, reflecting the neutron balance of the whole core. It is effective even the layer thickness is 1 or 2 cm. Compared with the conventional uniform introduction of this moderator into the seed, the fixed layer concept is more effective in reducing void reactivity and hardly deteriorate the breeding ratio. The negative void reactivity is proved for the non-flat large-sized radial heterogeneous core where the layers are placed between the seeds and blankets. The neutron absorption rate increases, the fast fission rate decreases in the central, inner and radial blankets.
- 一般社団法人 日本原子力学会の論文
著者
-
Koshizuka Seiichi
Nuclear Engineering Research Laboratory The University Of Tokyo
-
Oka Yoshiaki
Nuclear Engineering Research Laboratory Graduate School Of Engineering The University Of Tokyo
-
Koshizuka Seiichi
Nuclear Engineering Research Laboratory, The University of Tokyo
-
JEVREMOVIC Tatjana
Nuclear Engineering Research Laboratory, The University of Tokyo
-
JEVREMOVIC Tatjana
Nuclear Engineering Research Laboratory, Faculty of Engineering, 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
- Numerical Simulation of Drop Breakup by MPS 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.