Experimental Demonstration of Flow Diodes Applicable to a Passive Decay Heat Removal System for Sodium-Cooled Reactors

Chikazawa, Yoshitaka; Aizawa, Kosuke; Shiraishi, Taizo; Sakata, Hideyuki

doi:10.3327/jnst.46.321

Cited by 3 publications

(2 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…A fluidic diode is a passive flow control device with low flow resistance in one flow direction and high flow resistance in the opposite flow direction. A conventional vortex diode that has been tested by Chikazawa et al (2009) is adopted in the design. The fluidic diode has been oriented such that the flow will be in its reverse flow direction (upward direction in Fig.…”

Section: The Modular Prototypic Dracs Designmentioning

confidence: 99%

Scaling analysis for the direct reactor auxiliary cooling system for FHRs

Wang

Kim

et al. 2015

Nuclear Engineering and Design

View full text Add to dashboard Cite

Section: The Modular Prototypic Dracs Designmentioning

confidence: 99%

Scaling analysis for the direct reactor auxiliary cooling system for FHRs

Wang

Kim

et al. 2015

Nuclear Engineering and Design

View full text Add to dashboard Cite

“…For the fluidic valve, a value of 0.38 is taken for K, determined approximately from the study of Lv et al [31], and the area A d is assumed to be approximately 0.001 m 2 , such that the pressure loss in the reactor is approximately 330 Pa at 1.84 kg/s (see Ref. [22]).…”

mentioning

confidence: 99%

Transient freezing of molten salts in pipe-flow systems: Application to the direct reactor auxiliary cooling system (DRACS)

2017

View full text Add to dashboard Cite

The possibility of molten salt freezing in piping systems is a key concern for the solar energy industry and a safety issue in the new generation of molten-salt reactors worthy of careful consideration. This paper tackles the problem of coolant solidification in complex pipe networks by developing a transient thermohydraulic model and applying it to the 'Direct Reactor Auxiliary Cooling System' (DRACS), the passive safety system proposed for the generation-IV molten salt reactors. The results indicate that DRACS, as currently envisioned, is prone to failure due to freezing in the air/molten-salt heat exchanger. The occurrence of this scenario is related to an unstable behaviour mode of DRACS in which newly formed solid-salt deposit on the pipe walls acts to decrease the flow-rate in the secondary loop, facilitating additional solid-salt deposition. Conservative criteria are suggested to facilitate the preliminary assessments of DRACS designs. Such study is, to the knowledge of the authors, first in its type and it serves to illustrate the possible safety concerns in molten salt reactors, which are otherwise considered very safe in the literature. On a broader prospective, the analytical tools developed in this study can be used to model the freezing of molten salts in complex piping systems where standard, finite element approaches are computationally too expensive.

show abstract

On the Use of Selected 4th Generation Nuclear Reactors in Marine Power Plants

Drosińska-Komor

Głuch

Breńkacz

et al. 2022

Polish Maritime Research

View full text Add to dashboard Cite

This article provides a review of the possibility of using different types of reactors to power ships. The analyses were carried out for three different large vessels: a container ship, a liquid gas carrier and a bulk carrier. A novelty of this work is the analysis of the proposal to adapt marine power plants to ecological requirements in shipping by replacing the conventional propulsion system based on internal combustion engines with nuclear propulsion. The subjects of comparison are primarily the dimensions of the most important devices of the nuclear power plant and the preliminary fitness analysis. It was assumed for this purpose that the nuclear power plant fits in the engine room compartment and uses the space left after the removal of the combustion engines. At the same time, this propulsion provides at all times sufficient energy for port, technological and shipping operations at an economically justifiable speed. For deep-sea vessels, which are supposed to reach null emissions of CO, CO2, NOx, SOx and H2O, this is one of the most reasonable solutions. Finally the paper proves that all the above-mentioned marine functions could be effectively applied in power plants equipped with 4th generation nuclear reactors.

show abstract

Experimental Demonstration of Flow Diodes Applicable to a Passive Decay Heat Removal System for Sodium-Cooled Reactors

Cited by 3 publications

References 1 publication

Scaling analysis for the direct reactor auxiliary cooling system for FHRs

Scaling analysis for the direct reactor auxiliary cooling system for FHRs

Transient freezing of molten salts in pipe-flow systems: Application to the direct reactor auxiliary cooling system (DRACS)

On the Use of Selected 4th Generation Nuclear Reactors in Marine Power Plants

Contact Info

Product

Resources

About