Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
Fully natural circulation decay heat removal systems (DHRSs) are adopted for sodium fast reactors, which is a passive safety feature without any electrical pumps. It is needed to grasp the thermal-hydraulic phenomena in the reactor vessel and evaluate the coolability of the core under the natural ci...
Saved in:
Main Authors: | Ayako ONO, Masaaki TANAKA, Yasuhiro MIYAKE, Erina HAMASE, Toshiki EZURE |
---|---|
Format: | article |
Language: | EN |
Published: |
The Japan Society of Mechanical Engineers
2020
|
Subjects: | |
Online Access: | https://doaj.org/article/82e37c2ecfc6479795ae3d20a3b898d0 |
Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
Similar Items
-
Analysis of gas entrainment phenomenon from free liquid surface for a sodium-cooled fast reactor design (Velocity profile and Strouhal number in a flow field)
by: Mao UCHIDA, et al.
Published: (2021) -
Development of LORL evaluation method and its application to a loop-type sodium-cooled fast reactor
by: Yuya IMAIZUMI, et al.
Published: (2018) -
Heat transport analysis in a district heating system applying waste heat from GTHTR300, a commercial design of high-temperature gas-cooled reactor
by: Seiji KASAHARA, et al.
Published: (2016) -
Gas detection in sodium cooled fast reactors: determination of a transfer function
by: Ding C., et al.
Published: (2021) -
Development of a Fast-Spectrum Self-Powered Neutron Detector for Molten Salt Experiments in the Versatile Test Reactor
by: Goetz K. C., et al.
Published: (2021)