SCDAP/RELAP5 Evaluation of the Potential for Steam Generator Tube Ruptures as a Result of Severe Accidents in Operating PWRs

Knudson, D. L.; Ghan, L.S.; Dobbe, C.A.

doi:10.2172/911021

Cited by 6 publications

(5 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…As long as liquid remained in the Fig. 3 Surry reactor vessel nodalization [6] SG secondary, the (steady state) RCS subcooled margin in this case was essentially maintained. After SG secondary dry out, the heat transfer from the RCS was substantially reduced.…”

Section: Resultsmentioning

confidence: 87%

“…The RELAP5/SCDAPSIM input deck, which is the basis of our study, has been validated by several works, notably those of Knudson et al [6] and Siefken et al [7]. In Knudson et al work, the authors considered the effect of natural circulation flows that can develop in a reactor cooling system (RCS) during some reactor accidents, transferring the decay energy from the core to other parts of the RCS.…”

Section: Introductionmentioning

confidence: 92%

“…Surry pressurizer loop nodalization[6] COUPLE FE mesh used to model the lower head vessel (345 nodes and 308 elements) Pressure and liquid fraction in pressurizer for scenario #1 Mass flow rate of liquid and steam evacuated through PORVs and SRVs…”

mentioning

confidence: 99%

See 2 more Smart Citations

Numerical simulations of a creep rupture damage in Surry PWR primary circuit under TMLB accident

et al. 2020

View full text Add to dashboard Cite

In the nuclear safety field, the thermomechanical phenomena that occur during an accident in a nuclear power plant (NPP) are of particular importance. During some reactor severe accidents, the decay energy of the core is transferred via the reactor cooling system (RCS) to other parts of this circuit. The associated heatup of RCS structures can lead to pressure boundary failures; with notable vulnerabilities, i.e., the lower head vessel, the pressurizer surge line, the hot leg nozzles, etc. The potential for a primary circuit component rupture is of particular concern because fission products could be released into the environment by such a failure. The risk is higher in-vessel; the relocated debris toward the lower head vessel, following a potential melting of the core, leads to the rupture of the most important protective barrier. Primary circuit structures are subject to the effects of high pressure and high temperature throughout their service life. Such loadings generally lead to creep rupture. This risk is more likely when these structures experience transients or severe accidents. One of the most studied accidents is the station blackout (SBO). SBO without operator actions accident (TMLB' sequence) is considered as one of the most likely scenarios that may threaten the integrity of vulnerable RCS pressure boundaries. In this manuscript, we have evaluated, using the system code RELAP5/SCDAPSIM 3.4, the damage caused by rupture of some structures of the primary circuit of the Surry NPP. The structures analyzed are the surge line, the hot leg nozzles and the lower head vessel. RELAP5/SCDAPSIM 3.4 results indicate that surge line (hot leg) failures will be the first failures in the RCS pressure boundary.

show abstract

Section: Resultsmentioning

confidence: 87%

Section: Introductionmentioning

confidence: 92%

See 1 more Smart Citation

Numerical simulations of a creep rupture damage in Surry PWR primary circuit under TMLB accident

et al. 2020

View full text Add to dashboard Cite

show abstract

“…The whole approach is clearly a significant simplification of the complex and highly 3 dimensional flow pattern in question, with the changing flow rates and thermal conditions. However it is a common way of modelling when using the lump parameter codes (Liao and Vierow, 2005;Knudson et al, 1998), often combined with confirmatory analyses by detailed programs.…”

Section: Primary Circuit and Sg Modelmentioning

confidence: 99%

Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data

Rydl

Lind

Birchley

2016

Nuclear Engineering and Design

View full text Add to dashboard Cite

“…A molten debris pool is created in the bottom of the vessel, which is colder than the fuel, resulting in the instantaneous fuel solidification creating a crust, (Knudson Rempe, 2002). At this moment, because of the molten debris pool creation, the downcomers get blocked and the remaining water evaporates due to circulation termination.…”

Section: Vesselmentioning

confidence: 99%

External flooding event analysis in a PWR-W with MAAP5

Fernández-Cosials

Varas

Barreira

2015

Annals of Nuclear Energy

View full text Add to dashboard Cite

SCDAP/RELAP5 Evaluation of the Potential for Steam Generator Tube Ruptures as a Result of Severe Accidents in Operating PWRs

Cited by 6 publications

References 3 publications

Numerical simulations of a creep rupture damage in Surry PWR primary circuit under TMLB accident

Numerical simulations of a creep rupture damage in Surry PWR primary circuit under TMLB accident

Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data

External flooding event analysis in a PWR-W with MAAP5

Contact Info

Product

Resources

About