Analysis of metastable regimes in a parallel channel single phase natural circulation system with RELAP5/MOD3.2

Gartia, Manas Ranjan; Pilkhwal, D. S.; Vijayan, P.K.; Saha, Dilip

doi:10.1016/j.ijthermalsci.2006.11.016

Cited by 22 publications

(6 citation statements)

References 12 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Here, also the phenomenon of SGs inventory transfer from the affected loop to the healthy loop is observed, but the clad temperature shoots up far ahead of dryout due to PHT flow stagnation following PHT inventory transfer from affected loop to healthy loop. The results obtained with RELAP5 model show a similar behavior for natural circulation as reported in the literature [1][2][3][4]. It can be concluded that the 2 PHT loops should be isolated following an SBO to avoid inter-loop inventory transfer through the surge lines, which leads to stagnation of core flow in the affected loop due to unfavorable pressure distribution.…”

Section: Sbo Analysis With Only 3 Pdhrs Available and Without Pht Loosupporting

confidence: 80%

See 1 more Smart Citation

Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout

Gaikwad

Vijayan

Bhartya³

et al. 2008

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

Provision of passive means to reactor core decay heat removal enhances the nuclear power plant (NPP) safety and availability. In the earlier Indian pressurised heavy water reactors (IPHWRs), like the 220 MWe and the 540 MWe, crash cooldown from the steam generators (SGs) is resorted to mitigate consequences of station blackout (SBO). In the 700 MWe PHWR currently being designed an additional passive decay heat removal (PDHR) system is also incorporated to condense the steam generated in the boilers during a SBO. The sustainability of natural circulation in the various heat transport systems (i.e., primary heat transport (PHT), SGs, and PDHRs) under station blackout depends on the corresponding system's coolant inventories and the coolant circuit configurations (i.e., parallel paths and interconnections). On the primary side, the interconnection between the two primary loops plays an important role to sustain the natural circulation heat removal. On the secondary side, the steam lines interconnections and the initial inventory in the SGs prior to cooldown, that is, hooking up of the PDHRs are very important. This paper attempts to open up discussions on the concept and the core issues associated with passive systems which can provide continued heat sink during such accident scenarios. The discussions would include the criteria for design, and performance of such concepts already implemented and proposes schemes to be implemented in the proposed 700 MWe IPHWR. The designer feedbacks generated, and critical examination of performance analysis results for the added passive system to the existing generation II & III reactors will help ascertaining that these safety systems/inventories in fact perform in sustaining decay heat removal and augmenting safety.

show abstract

Section: Sbo Analysis With Only 3 Pdhrs Available and Without Pht Loosupporting

confidence: 80%

“…It has been reported in recent literature that RELAP5/ MOD3.2 is capable of simulating natural circulation phenomena [1][2][3][4]. The SG boil-off and SBO response for a PWR are described in detail [5].…”

Section: Passive Decay Heat Removal System (Pdhrs) For 700 Mwe Phwrmentioning

confidence: 99%

Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout

Gaikwad

Vijayan

Bhartya³

et al. 2008

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

show abstract

“…With natural convection in a large number of parallel heated channels that are fed by the same down comer, flow reversal is possible in low-power FAs [13]. This may lead to unstable natural circulation flow [14], and in some channels, the flow could be reduced and the cooling of the FAs perturbed, possibly leading to local nucleate boiling [15].…”

Section: Thermal-hydraulicsmentioning

confidence: 99%

Results of Validation and Cross-Verification of the ROK/B Design Code on the Problem of Loss of Cooling in the Spent Fuel Pool

Sledkov

Karnaukhov

Stepanov

et al. 2021

YadEn

View full text Add to dashboard Cite

The OECD is a unique forum where the governments of 36 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies.

show abstract

“…The RELAP5 code has been developed for BE transient simulation of light water reactor coolant systems during postulated accident. The code generalization enables its application to both nuclear and non-nuclear fields [18,23,27]. The code solves unsteady and one-dimensional mass, energy and momentum equations based upon a fast and semi-implicit finite-difference numerical scheme.…”

Section: Relap5/mod32 Computer Codementioning

confidence: 99%

“…It indicates the amount of water reserved in the steam generator drums, risers, and downcomers [27,28]. The drum level response to the accident depends on a combination of water and vapor dynamics inside the steam generator.…”

Section: Mitigated Scenariomentioning

confidence: 99%

Assessment of boiler tubes overheating mechanisms during a postulated loss of feedwater accident

Rahmani

Bouchami

Belaid

et al. 2009

Applied Thermal Engineering

View full text Add to dashboard Cite

Analysis of metastable regimes in a parallel channel single phase natural circulation system with RELAP5/MOD3.2

Cited by 22 publications

References 12 publications

Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout

Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout

Results of Validation and Cross-Verification of the ROK/B Design Code on the Problem of Loss of Cooling in the Spent Fuel Pool

Assessment of boiler tubes overheating mechanisms during a postulated loss of feedwater accident

Contact Info

Product

Resources

About