核聚变与等离子体物理
覈聚變與等離子體物理
핵취변여등리자체물리
NUCLEAR FUSION AND PLASMA PHYSICS
2014年
4期
320-325
,共6页
王小勇%栗再新%赵奉超%赵周%武兴华%王琦杰
王小勇%慄再新%趙奉超%趙週%武興華%王琦傑
왕소용%률재신%조봉초%조주%무흥화%왕기걸
聚变-快裂变增殖堆%包层%热工水力学%CFX软件
聚變-快裂變增殖堆%包層%熱工水力學%CFX軟件
취변-쾌렬변증식퇴%포층%열공수역학%CFX연건
Fusion-fission breeding reactor%Blanket%Thermal-hydraulics%CFX code
对新提出的套管结构聚变-快裂变增殖堆包层概念设计方案进行了热工水力学分析和设计,给出了典型的热工设计参数,并结合大型热工水力学软件CFX对其进行了温度场和压力分布的模拟分析。分析结果表明,材料温度均已低于许用温度,冷却剂出口温度高于773K,冷却剂压降也符合工程上的要求,初步验证了增殖堆包层设计的合理性。
對新提齣的套管結構聚變-快裂變增殖堆包層概唸設計方案進行瞭熱工水力學分析和設計,給齣瞭典型的熱工設計參數,併結閤大型熱工水力學軟件CFX對其進行瞭溫度場和壓力分佈的模擬分析。分析結果錶明,材料溫度均已低于許用溫度,冷卻劑齣口溫度高于773K,冷卻劑壓降也符閤工程上的要求,初步驗證瞭增殖堆包層設計的閤理性。
대신제출적투관결구취변-쾌렬변증식퇴포층개념설계방안진행료열공수역학분석화설계,급출료전형적열공설계삼수,병결합대형열공수역학연건CFX대기진행료온도장화압력분포적모의분석。분석결과표명,재료온도균이저우허용온도,냉각제출구온도고우773K,냉각제압강야부합공정상적요구,초보험증료증식퇴포층설계적합이성。
Thermal-hydraulic design and analysis for the new conceptual design of fusion-fission breeding reactor using casing pipes for fuel assembly was done. Based on typical thermal-hydraulic design parameters, preliminary thermal-hydraulic design for the blanket was proposed. The corresponding temperature distribution and pressure distribution were obtained using thermal-hydraulic codes, CFX. The simulation results showed that maximum temperature of the materials were all below their corresponding temperature limits, coolant temperature at the outlet was higher than 773℃, and pressure drop of the coolant could satisfy engineering requirement. The reasonability of this thermal-hydraulic design was preliminarily verified.