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钠冷行波堆和驻波堆堆芯特性对比分析

郑美银 陈平 李权 张大林 田文喜 苏光辉

原子能科学技术2018,Vol.52Issue(3):397-404,8.
原子能科学技术2018,Vol.52Issue(3):397-404,8.DOI:10.7538/yzk.2017.youxian.0389

钠冷行波堆和驻波堆堆芯特性对比分析

Constrastive Analysis of Core Characteristics for Sodium Cooled Traveling Wave Reactor and Standing Wave Reactor

郑美银 1陈平 2李权 1张大林 2田文喜 1苏光辉2

作者信息

  • 1. 核反应堆系统设计技术重点实验室,四川成都610213
  • 2. 中国核动力研究设计院,四川成都610213
  • 折叠

摘要

Abstract

A self-developed MCNP-ORIGEN coupled code MCORE was applied to perform neutronics and depletion calculations of the designed sodium cooled traveling wave reactor and standing wave reactor.Based on the power distribution obtained by MCORE,a self-developed sodium cooled fast reactor core steady state thermal-hydraulic analysis code SAST was applied to perform core thermal-hydraulic analysis of sodium cooled traveling wave reactor and standing wave reactor.The core physical and thermalhydraulic properties of sodium cooled traveling wave reactor and standing wave reactor were compared.The results show that standing wave reactor has advantages in burnup,maximum cladding and fuel temperatures,while traveling wave reactor has advantages in reactivity fluctuation and core outlet temperature uniformity.

关键词

行波堆/驻波堆/中子学/热工水力/对比分析

Key words

traveling wave reactor/standing wave reactor/neutronics/thermal-hydraulics/contrastive analysis

分类

能源科技

引用本文复制引用

郑美银,陈平,李权,张大林,田文喜,苏光辉..钠冷行波堆和驻波堆堆芯特性对比分析[J].原子能科学技术,2018,52(3):397-404,8.

原子能科学技术

OA北大核心CSCDCSTPCD

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