A comprehensive review of the leak flow through micro-cracks (in LBB) for nuclear system: morphologies and thermal-hydraulic characteristics

J Zhang, MJ Wang, Z Zhang, H Sun, YW Wu… - … Engineering and Design, 2020 - Elsevier
Piping cracks are widely spread in the nuclear system, which affects the safety and economy
of reactors. The leak before break (LBB) concept detects the leakage through cracks and …

A code development for leak before break (LBB) leakage from supercritical to subcritical conditions

J Zhang, RH Chen, MJ Wang, WX Tian, YW Wu… - Progress in Nuclear …, 2018 - Elsevier
The leak before break (LBB) concept plays an important role in reactor safety. A code
(LEABLE) for leak before break (LBB) leakage estimation was developed in this paper …

Prediction of LBB leakage for various conditions by genetic neural network and genetic algorithms

J Zhang, RH Chen, MJ Wang, WX Tian, GH Su… - … Engineering and Design, 2017 - Elsevier
In this study, three-layer Back Propagation Network (BPN) and Genetic Neural Network
(GNN) were applied to predict the leakage of Leak Before Break (LBB) for various …

Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR)

M Wang, S Qiu, G Su, W Tian - Applied thermal engineering, 2014 - Elsevier
Leak rate calculation is the foundation of Leak-Before-Break (LBB) technology application in
Pressurized Water Reactor (PWR). In the paper, a leak rate Mathcad calculation code with …

Study on the critical flow of removal pipe breakage in high-temperature gas-cooled reactor

H Dou, M Lang, Y Ji - Progress in Nuclear Energy, 2024 - Elsevier
Abstract Depressurized Loss of Force Cooling (DLOFC) accident resulting from breakage is
the worst condition in the safety analysis of high temperature gas-cooled reactor (HTR). The …

Numerical study on the thermal-hydraulic characteristics of the choked flow through micro cracks for various conditions

J Zhang, H Sun, M Wang, Y Wu, C Li, W Tian… - … Engineering and Design, 2020 - Elsevier
It's of great significant to figure out the detailed mechanisms of the leak flow through micro-
crack. Three-dimensional numerical simulation provides a visual and effective access to …

Artificial neural network introductions

J Zhang, G Su - Nuclear Power Plant Design and Analysis Codes, 2021 - Elsevier
The artificial intelligence has attracted broad attention and has been widely applied in the
field of nuclear engineering. This section introduce the artificial neural network (ANN) …

Transient pressure analysis for the reactor core and containment of a HTGR after a primary loop pressure boundary break accident

XW Li, XT Li, L Shi, SY He - Chinese Science Bulletin, 2011 - Springer
The pressure variances in the reactor core and containment of a High Temperature Gas-
cooled Reactor (HTGR) after a primary loop pressure boundary break accident determine …

Safety analysis for hot gas duct vessel in HTR-PM

X Li, X Li, L Shi, Z Zhang, S He - Nuclear Technology, 2011 - Taylor & Francis
The hot gas duct vessel (HGDV) is an important part of the high-temperature reactor–pebble-
bed module (HTR-PM) primary loop pressure boundary system. It connects the reactor …

Моделирование процесса истечения парогазовой смеси из дренажной магистрали ступени ракеты-носителя

КИ Жариков, ВИ Трушляков - Инженерно-физический журнал, 2019 - elibrary.ru
Рассмотрен процесс истечения парогазовой смеси (газ наддува и пары компонента
топлива) в среду с пониженным давлением на основе использования модели …