Experimental and analytical studies of boric acid concentrations in a VVER-440 reactor during the long-term cooling period of loss-of-coolant accidents

Tuunanen, Jari; Tuomisto, Heikki; Raussi, Pekka

doi:10.1016/0029-5493(94)90111-2

Cited by 23 publications

(9 citation statements)

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“…The boron tracking model was later implemented in CTF by Ozdemir (2012) [6] with the addition of cross flow between subchannels. The importance of entrained droplet field boric acid transport was highlighted in both the Westinghouse Precipitation Modes PRT Report of Kliem et al (2008) [7] and Tuunanen et al (1988) [8], and his group experimental studies of Tuunanen et al (1994) [9]. Therefore, the boron solute transient is calculated for both the continuous and entrained droplet fields (Freixa et al, 2007) [10].…”

Section: Boron Tracking and Precipitation Modeling 251 Boron Tracking Modelmentioning

confidence: 99%

CTF 4.0 Theory Manual

Salko¹,

Avramova

Wysocki³

et al. 2019

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Coolant-Boiling in Rod Arrays-Two Fluids (COBRA-TF) is a thermal/hydraulic (T/H) simulation code designed for light water reactor (LWR) vessel analysis. It uses a two-fluid, three-field (i.e. fluid film, fluid drops, and vapor) modeling approach. Both sub-channel and 3D Cartesian forms of 9 conservation equations are available for LWR modeling. The code was originally developed by Pacific Northwest Laboratory in 1980 and had been used and modified by several institutions over the last few decades.COBRA-TF also found use at the Pennsylvania State University (PSU) by the Reactor Dynamics and Fuel Modeling Group (RDFMG) and has been improved, updated, and subsequently re-branded as CTF. As part of the improvement process, it was necessary to generate su cient documentation for the open-source code which had lacked such material upon being adopted by RDFMG. This document serves mainly as a theory manual for CTF, detailing the many two-phase heat transfer, drag, and important accident scenario models contained in the code as well as the numerical solution process utilized. Coding of the models is also discussed, all with consideration for updates that have been made when transitioning from COBRA-TF to CTF. Further documentation outside of this manual is also available at RDFMG which focus on code input deck generation and source code global variable and module listings.

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Section: Boron Tracking and Precipitation Modeling 251 Boron Tracking Modelmentioning

confidence: 99%

CTF 4.0 Theory Manual

Salko¹,

Avramova

Wysocki³

et al. 2019

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show abstract

“…5). A number of studies are dedicated to investigation of thermal physics properties of buffer solutions of boric acid where sodium phosphate and hydroxide were used as the alkalinizing agents (Yassin Hassan et al 2015, Tuunanen et al 1992. However, parameters of the investigated coolant do not correspond to water-chemistry operational conditions of NPPs equipped with VVER reactors and, besides that, similarly to the preceding papers investigation was conducted at fairly low concentrations of boric acid.…”

Section: Thermal Physics Properties Of Boric Acid Solutionsmentioning

confidence: 99%

“…Condensation capacity of steam generators was obtained from the results of experimental studies conducted on large-scale testing facility at the SSC RF-IPPE (Tuunanen et al 1992 where N PHRS is the condensation capacity of steam generator, kW; t is the time, s. Residual heat energy in the reactor core will be spent on evaporation of solution supplied in the core from RPC:…”

Section: Calculation Of Evolution Of Concentration Of Boric Acid In Tmentioning

confidence: 99%

Estimation influence of boric acid drop entrainment to its accumulation in the VVER reactor in the case of accident

Morozov¹,

Pityk²,

Ragulin³

et al. 2018

NUCET

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Process of boric acid mass transfer during accidents accompanied with rupture of circulation pipelines in VVER reactors of new generation equipped with passive safety systems are examined. Results of calculation of variation of boric acid concentration in VVER-TOI reactor in case of accident development process are presented. Positive effects of boric acid droplet entrainment on the processes of acid accumulation and crystallization in the reactor core are demonstrated. The obtained results allow formulating the conclusion on the possibility of these processes in the reactor core which may lead to the disruption of heat removal from fuel pins. Review of available published reference data on physical properties of boric acid solutions (density, viscosity, thermal conductivity) is given. It is established that available information is of too general nature and fails to cover the whole range of parameters (acid temperature, pressure and concentration) typical for potential emergency situation on NPP equipped with VVER reactor. Necessity of experimental study of processes of droplet entrainment under parameters typical for VVER emergency operation conditions, as well as investigation of thermal physics properties of boric acid within wide range of acid concentration values is required.

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“…The boron tracking model was later implemented in CTF by Ozdemir (2012) [63] with the addition of cross flow between subchannels. The importance of entrained droplet field boric acid transport was highlighted in both the Westinghouse Precipitation Modes PRT Report of Kliem et al (2008) [50] and Tuunanen et al (1988) [89], and his group experimental studies of Tuunanen et al (1994) [90]. Therefore, the boron solute transient is calculated for both the continuous and entrained droplet fields (Freixa et al, 2007) [23].…”

Section: Boron Tracking and Precipitation Modeling 251 Boron Tracking Modelmentioning

confidence: 99%

CTF Theory Manual

Avramova

Salko

2016

View full text Add to dashboard Cite

Coolant-Boiling in Rod Arrays-Two Fluids (COBRA-TF) is a thermal/ hydraulic (T/H) simulation code designed for light water reactor (LWR) vessel analysis. It uses a two-fluid, three-field (i.e. fluid film, fluid drops, and vapor) modeling approach. Both sub-channel and 3D Cartesian forms of 9 conservation equations are available for LWR modeling. The code was originally developed by Pacific Northwest Laboratory in 1980 and had been used and modified by several institutions over the last few decades.COBRA-TF also found use at the Pennsylvania State University (PSU) by the Reactor Dynamics and Fuel Management Group (RDFMG) and has been improved, updated, and subsequently re-branded as CTF. As part of the improvement process, it was necessary to generate sufficient documentation for the open-source code which had lacked such material upon being adopted by RDFMG. This document serves mainly as a theory manual for CTF, detailing the many two-phase heat transfer, drag, and important accident scenario models contained in the code as well as the numerical solution process utilized. Coding of the models is also discussed, all with consideration for updates that have been made when transitioning from COBRA-TF to CTF. Further documentation outside of this manual is also available at RDFMG which focus on code input deck generation and source code global variable and module listings.

show abstract

Experimental and analytical studies of boric acid concentrations in a VVER-440 reactor during the long-term cooling period of loss-of-coolant accidents

Cited by 23 publications

References 0 publications

CTF 4.0 Theory Manual

CTF 4.0 Theory Manual

Estimation influence of boric acid drop entrainment to its accumulation in the VVER reactor in the case of accident

CTF Theory Manual

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