Results 51 to 60 of about 5,620 (304)

Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and fluent

Nukleonika, 2015
Three-dimensional simulations of neutronics and thermal hydraulics of nuclear reactors are a tool used to design nuclear reactors. The coupling of MCB and FLUENT is presented, MCB allows to simulate neutronics, whereas FLUENT is computational fluid ...
Królikowski Igor P., Cetnar Jerzy
doaj   +1 more source

Coupled Monte Carlo and Thermal-Hydraulics Modeling for the Three-Dimensional Steady-State Analysis of the Xi’an Pulsed Reactor

Energies, 2023
The Xi’an Pulsed Reactor (XAPR) is characterized by its small core size and integrated fuel moderator structure, which results in a non-uniform core power and temperature distribution. Consequently, a complex coupling relationship exists between its core
Duoyu Jiang, Peng Xu, Tianliang Hu, Xinbiao Jiang, Lipeng Wang, Da Li, Xinyi Zhang, Lu Cao   +7 more
doaj   +1 more source

Influence of Si Content and Milling Duration on the Microstructure and Mechanical–Tribological Properties of AlCoCrFeNiSi High‐Entropy Alloys

Advanced Engineering Materials, EarlyView.
Si‐doped AlCoCrFeNi high‐entropy alloys are synthesized by mechanical alloying to reveal the effect of Si content and milling time on phase evolution, microstructural refinement, and tribological behavior. A transition from FCC to BCC structure, significant grain refinement, and enhanced hardness and wear resistance are achieved, with the 4 at% Si ...
Mustafa Okumuş, Mehmet Emin Demir, Sercan Özpınar   +2 more
wiley   +1 more source

ANALYSIS OF UNCERTAINTY QUANTIFICATION METHOD BY COMPARING MONTE-CARLO METHOD AND WILKS’ FORMULA

Nuclear Engineering and Technology, 2014
An analysis of the uncertainty quantification related to LBLOCA using the Monte-Carlo calculation has been performed and compared with the tolerance level determined by the Wilks’ formula.
SEUNG WOOK LEE, BUB DONG CHUNG, YOUNG-SEOK BANG, SUNG WON BAE   +3 more
doaj   +1 more source

Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

Nuclear Engineering and Technology, 2023
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang   +11 more
doaj   +1 more source

Thoughts in nuclear thermal hydraulics [PDF]

, 2016
Open thoughts for progressin in nuclear thermal hydraulics - brainstorming meeting (selected ...
D'Auria Francesco
core  

Multimodal Soft Surgical Robots Enabled by Eco‐Degradable, Sterilizable Polymers and Transient Electronics

Advanced Functional Materials, EarlyView.
A compostable PGS soft surgical robot with interchangeable modules integrates transient Mo tactile and Si thermal sensors for dual feedback. The device preserves its function after clinical‐grade sterilization, demonstrates stable actuation and cardiac tissue grasping with real‐time in vivo pulsatile monitoring, and biodegrades post‐use with soil‐safe, 
Minseong Chae, Kyung‐Sub Kim, Gyeong‐Seok Hwang, Jun‐Seok Shim, Sung‐Woo Kim, Yong‐Wu Kim, Jieun Han, Jae‐Young Bae, Jae‐Hwan Lee, Minjung Chae, Jooik Jeon, Joo‐Hyeon Park, You‐Jung Park, Ju‐Yong Lee, Sung‐Geun Choi, Min‐Ha Oh, Yong‐Joong Shin, Young‐In Ryu, Ji‐Woo Gu, Seong‐Yu Choi, Jeong‐Yun Sun, Jung Keun Hyun, Myoung‐Ryul Ok, Sang Yup Kim, Edyta Wyszkowska, Ju‐Young Kim, Kang‐Sik Lee, Seung‐Kyun Kang   +27 more
wiley   +1 more source

Study on the Calculation Method of Molten Pool Decay Heat Distribution under IVR Condition

Frontiers in Energy Research, 2021
As an important strategy to mitigate severe accidents, the in-vessel retention (IVR) technique has been applied to the new generation of pressurized water reactor (PWR).
Yisheng Hao, Junyi Chen, Hao Luo, Xiaoyu Guo, Minyun Liu, Minyun Liu, Shanfang Huang, Kan Wang, Houjun Gong, Yang Li, Yuwen Hu, Chuan Lu   +11 more
doaj   +1 more source

SESAR Group: Thermal Hydraulics Outcomes

, 2020
The present report deals with the perspectives in nuclear thermal hydraulics envisaged by a Senior Group of Experts (SESAR) of the Committee on the Safety of Nuclear Installations (CSNI) of the Nuclear Energy Agency (NEA) of Organization for Economic ...
F. Barré, F. D'Auria
core  

A historical perspective of nuclear thermal-hydraulics - Chapter 2

, 2017
Three main topics are concerned: (a) the definition of system thermal-hydraulics, (b) a historical outline, (c) elements for reflection when planning researches or improvement activities.
D'Auria Francesco Saverio, F. D'Auria
core   +1 more source