2012, Volume 14, Issue 8
Strategic Study of CAE >> 2012, Volume 14, Issue 8
Analysis of the core thermal-hydraulic characteristics of in-hospital neutron irradiatormark 1 reactor
1. Northwest Institute of Nuclear Technology, Xi'an 710024, China;
2. China Zhongyuan Engineering Corporation, China National Nuclear Corporation, Beijing 100191, China
Next Previous
Abstract
According to the characteristics and operation condition of IHNI-1 reactor, a subchannel model is developed in this paper. It also has been verified that the model is reasonable and effective in IHNI-1's thermal hydraulic analysis. Using the model, some thermal parameters of IHNI-1reactor are calculated. The relation between the core's coolant inlet flux and outlet temperature is analyzed, and the variation of rod temperature with reactor power is also calculated.
Keywords
IHNI-1 reactor ; thermal-hydraulic ; subchannel ; safety analysis
Figures
图1
图2
图3
图4
图5
图6
图7
图8
图9
图10
References
[ 1 ] 江新标，张文首，高集金，等.低浓化医院中子照射器（HNI-1）堆芯的物理方案设计[J].中国工程科学，2009，11（11）：17一21. link1
[ 2 ] 陈立新，张颖，陈伟，等。子通道程序PRTHA在西安脉冲堆上的应用[J].核动力工程，2003，24（6增刊）：56-59. link1
[ 3 ] 杨世铭，陶文.传热学（第四版）[M].北京：高等教育出版社，2006.
[ 4 ] 陈淑林，冷贵君.低压临界热流密度公式评述[J].核动力工程，1995，16（2）：135-140. link1
[ 5 ] Kennedy GJ，St Pierre.Leu-fuelled slowpoke-2 research reactors:operational experience and utilization[C]//2002 Intermational Meeting on Reduced Enrichment for Research and Test Reactors，San Carlos de Bariloche，Argentina，2002：1-3.
京公网安备 11010502051620号
