Thermal-Hydraulic System Study of the Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) for ITER Using System Code RELAP5-Reference-Cited by-同舟云学术

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Thermal-Hydraulic System Study of the Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) for ITER Using System Code RELAP5

Published:2005-04 Issue:2 Volume:7 Page:2753-2757
ISSN:1009-0630
Container-title:Plasma Science and Technology
language:
Short-container-title:Plasma Sci. Tech.

Author:

Xuezhou Jin,Meyder R

Publisher

IOP Publishing

Subject

Condensed Matter Physics

Reference4 articles.

Cited by 11 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Preliminary thermal-hydraulic analysis of the EU-DEMO Helium-Cooled Pebble Bed fusion reactor by using the RELAP5-3D system code;Fusion Engineering and Design;2021-01

2. Primary heat transfer system design of the WCCB blanket for multiple operation modes of CFETR;Fusion Engineering and Design;2020-04

3. Study on normal operation and failure of pressure control for CN HCCB TBS primary coolant system;Fusion Engineering and Design;2019-07

4. Steady State and Transient Analysis of Novel Design Helium Cooled Ceramic Blanket (HCCB) System of China Fusion Engineering Test Reactor (CFETR);Journal of Fusion Energy;2018-09-14

5. Thermal hydraulic responses of the Primary Heat Transfer System of the WCCB blanket to accident cases for CFETR;Fusion Engineering and Design;2017-10

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