Science and Technology of Nuclear Installations

Safety Features of High Temperature Gas Cooled Reactor


Status
Published

Lead Editor
Guest Editors

1Tsinghua University, Beijing, China

2Oak Ridge National Laboratory, Oak Ridge, USA


Safety Features of High Temperature Gas Cooled Reactor

Description

Modular High Temperature Gas Cooled Reactor (HTGR) is considered as a kind of catastrophe free nuclear reactor and because of its meltdown-immune feature, the practical elimination of large radioactive release from nuclear power plants becomes reliable with this technology. Following the concept of design to safety, the first demonstration project of modular HTGR in the world (HTR-PM) is under construction in Shidao Bay (in Shandong, China) and is planned to operate at the end of 2017. With advances in engineering of modular HTGR, the studies of safety features of HTGR also deepen step by step. Recently, there are lots of academic achievements related to the field of HTGR safety features, including beyond design basis accident (BDBA) of HTGR, multiscale source term analysis of HTGR, behavior of tritium in primary and secondary circuit of HTGR, and minimizing emergency for modular HTGR, which is essential for the future improvements of the design, operation, and maintenance of the modular HTGR.

The main aim of this special issue is to provide a platform for sharing the latest and significant research achievements on safety features of HTGR. Original research articles on topics mentioned above are welcomed and other related studies are also solicited.

Potential topics include but are not limited to the following:

  • Performances of HTGR fuel
  • Safety and accident analysis of HTGR (reactor physics analysis, thermal-hydraulics analysis, and PSA)
  • Source term analysis of HTGR
  • Control of multimodular HTGRs and related human factor analysis
  • Optimizing radiation protection of HTGR
  • Emergency management of HTGR

Articles

  • Special Issue
  • - Volume 2017
  • - Article ID 6298037
  • - Research Article

Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant

Zhe Dong | Yifei Pan | ... | Zuoyi Zhang
  • Special Issue
  • - Volume 2017
  • - Article ID 2126876
  • - Research Article

The Electric Current Effect on Electrochemical Deconsolidation of Spherical Fuel Elements

Xiaotong Chen | Zhenming Lu | ... | Chunhe Tang
  • Special Issue
  • - Volume 2017
  • - Article ID 2416545
  • - Research Article

A New Method to Measure Crack Extension in Nuclear Graphite Based on Digital Image Correlation

Shigang Lai | Li Shi | ... | Zhengming Zhang
  • Special Issue
  • - Volume 2017
  • - Article ID 5403701
  • - Research Article

Research on the Computed Tomography Pebble Flow Detecting System for HTR-PM

Xin Wan | Ximing Liu | ... | Zhifang Wu
  • Special Issue
  • - Volume 2017
  • - Article ID 8918424
  • - Research Article

Physical Analysis of the Initial Core and Running-In Phase for Pebble-Bed Reactor HTR-PM

Jingyu Zhang | Fu Li | Yuliang Sun
  • Special Issue
  • - Volume 2017
  • - Article ID 2614890
  • - Research Article

Source Term Analysis of the Irradiated Graphite in the Core of HTR-10

Xuegang Liu | Xin Huang | ... | Hong Li
  • Special Issue
  • - Volume 2017
  • - Article ID 8296387
  • - Research Article

Adsorption Behaviors of Cobalt on the Graphite and SiC Surface: A First-Principles Study

Wenyi Wang | Chuan Li | ... | Chao Fang
  • Special Issue
  • - Volume 2017
  • - Article ID 3857075
  • - Research Article

3D Nondestructive Visualization and Evaluation of TRISO Particles Distribution in HTGR Fuel Pebbles Using Cone-Beam Computed Tomography

Gongyi Yu | Yi Du | ... | Xiangang Wang
Science and Technology of Nuclear Installations
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Acceptance rate32%
Submission to final decision60 days
Acceptance to publication39 days
CiteScore1.700
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