Journal ArticleDOI
Study on Pb-Bi natural circulation phenomena
TLDR
In this paper, an experimental study on Pb-Bi water direct contact boiling two-phase flow has been performed using PbBi-water direct contact boil water small fast reactor (PBWFR), where a stable single-phase natural circulation was realized in the range of flow rate from 1.5 l/min to 4.8 l /min by heating Pb Bi in the heaterpin bundle with a power up to 7.7 kW.About:
This article is published in Progress in Nuclear Energy.The article was published on 2005-01-01. It has received 20 citations till now. The article focuses on the topics: Thermal mass flow meter & Boiling.read more
Citations
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Journal ArticleDOI
Natural circulation studies in a lead bismuth eutectic loop
A. Borgohain,B. K. Jaiswal,Naresh Kumar Maheshwari,Pallippattu Krishnan Vijayan,D. Saha,R. K. Sinha +5 more
TL;DR: In this paper, a 1D code named LeBENC has been developed at BARC to simulate the natural circulation characteristics in closed loops, including ability to handle non-uniform diameter components, axial thermal conduction in fluid and heat losses from the piping to the environment.
Journal ArticleDOI
Role of thorium in the Indian nuclear power programme
TL;DR: The thorium fuel cycle based Advanced Heavy Water Reactor (AHWR) is being developed in this paper for large-scale deployment of thorium-based nuclear power plants in India.
Journal ArticleDOI
Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR)
TL;DR: In this paper, a new computer code is developed to investigate the thermal-hydraulic behaviors and safety performance of PBWFR in the present work, and the results show that PBW FR has very good inherent safety due to the satisfactory neutron and thermal-physical properties of LBE.
Journal ArticleDOI
Experimental studies and computational benchmark on heavy liquid metal natural circulation in a full height-scale test loop for small modular reactors
Yong-Hoon Shin,Jaehyun Cho,Ju-Eun Lee,Heejae Ju,Sungjune Sohn,Yeji Kim,Hyunyub Noh,Il Soon Hwang +7 more
TL;DR: In this paper, the authors present results of experiments with LBE non-isothermal natural circulation in a full-height scale test loop, HELIOS (heavy eutectic liquid metal loop for integral test of operability and safety of PEACER).
Journal ArticleDOI
Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes
TL;DR: In this article, a Pb-Bi cooled direct-contact-boiling water fast-reactor (PBWFR) is studied and coupled thermal-hydraulic analysis with the in-house system analysis code SACOL and sub-channel analysis code SUBAS is conducted using the one-direction multi-step coupling method.
References
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A feasibility study on the Pb-Bi cooled direct contact boiling water fast reactor
TL;DR: The Pb-Bi cooled direct contact boiling water fast (PBWFR) as mentioned in this paper can produce the steam by direct contact with primary PbBi coolant and feed water in the upper core plenum, and recirculate Pb Bi coolant by the buoyancy of steam.
Design and Experimental Study for Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR)
M. Takahashi,Toru Obara,T. Iguchi,A. Otsubo,Masatoshi Kondo,Y. Qi,M. Matsumoto,Elin Yusibani,T. Akashi,A. Yamada,H. Nei,Koji Hata,K. Hara,S. Uchida,Hiroo Osada,Yoshiyuki Kasahara,K. Matsuzawa,N. Sawa,Y. Yamada,K. Kurome,Y. Okubo +20 more