Effect of Heat Exchange Area Margins on Thermal Characteristics of the Heat Exchange System in the Pressurized Water Test Loop during Fuel Assembly Irradiation

Author:

Si Junping1ORCID,Zhao Guang1,Wang Yun1,Sun Sheng1,Tong Mingyan1,Zhu Wei1,Lei Jin1,Cheng Jinkang1,Song Yueyan1,Lu Mengkang1

Affiliation:

1. Reactor Operation and Application Research Sub-Institute, Nuclear Power Institute of China, Chengdu 610213, China

Abstract

The performance of heat exchangers in the pressurized water test loop is a critical factor in ensuring the achievement of irradiation parameters for fuel assemblies and the safety of experimental operations. The effect of the heat exchange area margin on the heat exchangers in the pressurized water test loop for the fuel assembly during the steady-state irradiation is analyzed. Additionally, optimization methods for determining the margin of heat exchange area and corresponding design strategies are further investigated. It shows that the effect of the heat exchange area margin on the heat exchange power is less affected by the inlet temperature of the primary water and is primarily influenced by the flow rate of the primary water. A decrease in the flow rate of the primary water reduces the compensatory effect of the cooling section on power and enhances the weakening effect of the regeneration section on power. Meanwhile, the correspondence between the margin of the regeneration section and the cooling section, established based on design conditions, can be applicable when there are changes in the inlet temperature of the primary water, but it is not suitable when there are changes in the flow rate of the primary water. When the flow rate of the primary water decreases, the cooling section margin required to compensate for the decrease in power caused by the regeneration section margin will increase significantly. In addition, short-circuiting the heat exchange tubes in the regeneration section can effectively enhance the heat transfer capability. Furthermore, setting the heat exchange area margins of the regeneration and cooling sections to zero can serve as a termination condition for iterative calculations in the verification of regenerative heat exchangers under off-design conditions.

Funder

Nuclear Power Institute of China Basic Research Fund

Publisher

MDPI AG

Reference28 articles.

1. Investigation of safety aspects during steady state operation of Tehran research reactor fuel test loop;Arshi;Prog. Nucl. Energy,2021

2. Irradiation experiments of titanium beryllide samples in the WWR-K reactor;Shaimerdenov;Ann. Nucl. Energy,2023

3. Mechanical strength of CTP Triplex SiC fuel clad tubes after irradiation in MIT research reactor under PWR coolant conditions;Feinroth;Ceram. Eng. Sci. Proc,2009

4. Neutron radiography and tomography applied to fuel degradation during ramp tests and loss of coolant accident tests in a research reactor;Jenssen;Prog. Nucl. Energy,2014

5. Rempe, J.L., Knudson, D.L., and Daw, J.E. (2011). Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations, Idaho National Lab. (INL). No. INL/EXT-11-21231.

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3