Jiandi Guo , Zhouyu Liu , Qingming He , Danbin Huang , Liangzhi Cao , Hongchun Wu
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引用次数: 0
Abstract
Since secondary neutron sources in Pressurized Water Reactors (PWRs) continuously produce tritium, the technology of replacing these sources with spent fuel assemblies has been proposed to reduce such emissions. To this end, this study introduces a Monte-Carlo-Deterministic coupling simulation approach for the Hualong One start-up without secondary neutron sources, utilizing NECP-MCX and Bamboo-C. Firstly, the Monte Carlo model was refined by criticality calculation and the thermal neutron sensitivity coefficient of the detectors was then calibrated. The approach was subsequently validated through analysis of the calibration experiments utilizing secondary neutron sources during Cycle 2 fuel loading process. Finally, the count rate of ex-core source-range detectors with spent fuel assembly neutron sources was predicted. The results indicate that the maximum relative error of the source-range detector count rate during the Cycle 2 calibration experiments is 11.11 %. The results further predict that placing a spent fuel assembly with a burnup of 29.39 GWd/tU at position R06 or R08 within the reactor core will satisfy the requirements for the Hualong One start-up. In summary, the simulation approach presented in this paper provides theoretical support for the Hualong One start-up in the absence of secondary neutron sources and contributes to reducing tritium emissions.
期刊介绍:
Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters.
NET covers all fields for peaceful utilization of nuclear energy and radiation as follows:
1) Reactor Physics
2) Thermal Hydraulics
3) Nuclear Safety
4) Nuclear I&C
5) Nuclear Physics, Fusion, and Laser Technology
6) Nuclear Fuel Cycle and Radioactive Waste Management
7) Nuclear Fuel and Reactor Materials
8) Radiation Application
9) Radiation Protection
10) Nuclear Structural Analysis and Plant Management & Maintenance
11) Nuclear Policy, Economics, and Human Resource Development