Results 31 to 40 of about 21,387 (164)

Natural circulation characteristics of main loop after shutdown of liquid-fuel molten salt reactor

He jishu
BackgroundThe molten salt reactor (MSR) is one of the six advanced reactors identified by the Generation IV International Forum. The MSR exhibits unique characteristics, such as intrinsic safety, sustainable development, nuclear nonproliferation, natural
XUE Shuaiyu, ZHOU Chong, ZOU Yang, XU Hongjie   +3 more
doaj   +1 more source

Modeling of natural circulation for the inherent safety analysis of sodium cooled fast reactors

Nuclear Energy and Technology, 2016
The paper discusses a set of developed integrated one-dimensional models of thermal-hydraulic processes that contribute to the removal of decay heat in a BN-type reactor.
A.S. Bochkarev, P.N. Alekseev, A.S. Korsun, V.S. Kharitonov   +3 more
doaj   +1 more source

Safety analysis of increase in heat removal from reactor coolant system with inadvertent operation of passive residual heat removal at no-load conditions

Nuclear Engineering and Technology, 2015
The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive residual heat removal (PRHR) system was designed to remove the decay heat. During accident scenarios with increase of heat removal from the primary coolant
Ge Shao, Xuewu Cao
doaj   +1 more source

Design of a direct-cycle supercritical CO2 nuclear reactor with heavy water moderation

Nuclear Engineering and Technology, 2022
A new reactor concept is described that directly couples a supercritical CO2 (sCO2) power cycle with a CO2-cooled, heavy water moderated pressure tube core.
Robert Petroski, Ethan Bates, Benoit Dionne, Brian Johnson, Alex Mieloszyk, Cheng Xu, Pavel Hejzlar   +6 more
doaj   +1 more source

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

Mechanical Engineering Journal, 2020
Fully natural circulation decay heat removal systems (DHRSs) are adopted for sodium fast reactors, which is a passive safety feature without any electrical pumps.
Ayako ONO, Masaaki TANAKA, Yasuhiro MIYAKE, Erina HAMASE, Toshiki EZURE   +4 more
doaj   +1 more source

Application of Chernoff bound to passive system reliability evaluation for probabilistic safety assessment of nuclear power plants

Nuclear Engineering and Technology, 2022
There is an increasing interest in passive safety systems to minimize the need for operator intervention or external power sources in nuclear power plants. Because a passive system has a weak driving force, there is greater uncertainty in the performance
Eunseo So, Man Cheol Kim
doaj   +1 more source

Research on Design of Natural Circulation Decay Heat Removal for Pool-type Sodium-cooled Fast Reactor

Yuanzineng kexue jishu
Based on the design parameters of the core decay heat removal through natural circulation of the typical high-power sodium-cooled fast reactor, using the system analysis program ERAC, a detailed analysis of the reactor core decay heat removal process ...
ZHOU Zhiwei, XUE Xiuli, LIN Chao, YU Xintai, YANG Yong, YANG Hongyi
doaj   +1 more source

PENINGKATAN KINERJA SISTEM KESELAMATAN PASIF PADA REAKTOR NUKLIR DENGAN PENAMBAHAN KOMPONEN RVACS

Jurnal Pendidikan Fisika Indonesia, 2014
Kelengkapan sistem keselamatan pasif dan inheren pada reaktor lanjut merupakan prasyarat utama. Makalah ini mengeksplorasi hasil desain konseptual sistem pembuang sisa panas pada pusat listrik tenaga nuklir berjenis Very High-Temperature Reactor.
A. G. Abdullah, N. P. Ardiansyah, W. Purnama   +2 more
doaj   +1 more source

COMPARISON OF THE DECAY HEAT REMOVAL SYSTEMS IN THE KALIMER-600 AND DSFR [PDF]

Nuclear Engineering and Technology, 2012
A sodium-cooled demonstration fast reactor with the KALIMER-600 as a reference plant is under design by KAERI. The safety grade decay heat removal system (DHRS), which is important to mitigate design basis accidents, was changed in the reactor design.
Kwi-Seok Ha, Hae-Yong Jeong
openaire   +1 more source

Modelling of Heat Transfer Phenomena for Vertical and Horizontal Configurations of In-Pool Condensers and Comparison with Experimental Findings

Science and Technology of Nuclear Installations, 2010
Decay Heat Removal (DHR) is a fundamental safety function which is often accomplished in the advanced LWRs relying on natural phenomena. A typical passive DHR system is the two-phase flow, natural circulation, closed loop system, where heat is removed by
Davide Papini, Antonio Cammi
doaj   +1 more source