Total loss of AC power analysis for EPR reactor

Darnowski, Piotr; Skrzypek, Eleonora; Mazgaj, Piotr; Świrski, Konrad; Gandrille, Pascal

doi:10.1016/j.nucengdes.2015.03.020

Cited by 8 publications

(6 citation statements)

References 13 publications

(18 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The observation supports that a large variation of hydrogen production can be found among different MELCOR references in the literature, and it may be confusing for analysts or researchers. What is more, a lower mass for PWR [14] or a larger mass for BWR [15,16] can be predicted, and results can vary when different code versions are used. The code typically produces a different hydrogen mass than other severe accident codes, especially MAAP code, and it commonly puzzles code users.…”

Section: Scope and Motivationmentioning

confidence: 99%

“…Other plant details were also modelled, including the mai steam line with safety valves, the pressurizer with safety valves and accident valves, th The COR package model has nineteen axial levels and six rings. The active core region has twelve axial levels (7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18) and one non-active fuel level above and below the active core (6 and 19). The core support plate is modelled by level 5, and the levels below are part of the lower plenum.…”

Section: Gen-iii Pwr Modelmentioning

confidence: 99%

“…The model has two loops; one is a single loop with a pressurizer, called "broken," and the second is a combination of three other loops, and it is called "intact." The nodalization strategy is based on previous research [14,33]. Other plant details were also modelled, including the main steam line with safety valves, the pressurizer with safety valves and accident valves, the pressurizer relief tank connected with the containment, passive accumulators, main feedwater and auxiliary feedwater systems.…”

Section: Gen-iii Pwr Modelmentioning

confidence: 99%

See 2 more Smart Citations

Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2

2021

Self Cite

View full text Add to dashboard Cite

In this study, uncertainty and sensitivity analyses were performed with MELCOR 2.2.18 to study the hydrogen generation (figure-of-merit (FoM)) during the in-vessel phase of a severe accident in a light water reactor. The focus of this work was laid on a large generation-III pressurized water reactor (PWR) and a double-ended hot leg (HL) large break loss of coolant accident (LB-LOCA) without a safety injection (SI). The FPT-1 Phebus integral experiment emulating LOCA was studied, where the experiment outcomes were applied for the plant scale modelling. The best estimate calculations were supplemented with an uncertainty analysis (UA) based on 400 input-decks and Latin hypercube sampling (LHS). Additionally, the sensitivity analysis (SA) utilizing the linear regression and linear and rank correlation coefficients was performed. The study was prepared with a new open-source MELCOR sensitivity and uncertainty tool (MelSUA), which was supplemented with this work. The FPT-1 best-estimate model results were within the 10% experimental uncertainty band for the final FoM. It was shown that the hydrogen generation uncertainties in PWR were similar to the FPT-1, with the 95% percentile being covered inside a ~50% band and the 50% percentile inside a ~25% band around the FoM median. Two different power profiles for PWR were compared, indicating its impact on the uncertainty but also on the sensitivity results. Despite a similar setup, different uncertainty parameters impacted FoM, showing the difference between scales but also a significant impact of boundary conditions on the sensitivity analysis.

show abstract

Section: Scope and Motivationmentioning

confidence: 99%

Section: Gen-iii Pwr Modelmentioning

confidence: 99%

Section: Gen-iii Pwr Modelmentioning

confidence: 99%

See 1 more Smart Citation

Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2

2021

Self Cite

View full text Add to dashboard Cite

show abstract

“…Continuing for illustrative purposes, high fidelity modeling of reactor thermohydraulics is a key component of the overall accuracy of RUAS water resupply to the SFP. Sandia National Lab's MELCOR model is extensively tested, verified, and widely use in the literature (Wang et al 2005;Darnowski et al 2015;Fernandez-Moguel 2015;Fernandez-Moguel and Birchley 2015;Polo-Labarrios and Espinosa-Paredes 2015;Sevón 2015;Wang et al 2015a,b). Figure 5 indicates MELCOR providing Figure 4 Reactor/SFP functionality.…”

Section: Lvc Simulation Frameworkmentioning

confidence: 99%

A Systems-Of-Systems Conceptual Model and Live Virtual Constructive Simulation Framework for Improved Nuclear Disaster Emergency Preparedness, Response, and Mitigation

Davis

Proctor

Shageer

2016

Journal of Homeland Security and Emergency Management

View full text Add to dashboard Cite

Nuclear disasters have severe and far-reaching consequences. Emergency managers and first responders from utility owners to local, state, and federal civil authorities and the Department of Defense (DoD) must be well prepared in order to rapidly mitigate the disaster and protect the public and environment from spreading damage. Given the high risks, modeling and simulation (M&S) plays a significant role in planning and training for the spectrum of derivate scenarios. Existing reactor models are largely legacy, stove-piped designs lacking interoperability between themselves and other M&S tools for emergency preparedness system evaluation and training. Unmanned systems present a growing area of technology promising significant improvement in response and mitigation. To bridge the gap between current and future models, we propose a conceptual model (CM) for integrating live, virtual, and constructive (LVC) models with nuclear disaster and mitigation models utilizing a system-ofsystems (SoS) approach. The CM offers to synergistically enhance current reactor and dispersion simulations with intervening avatar and agent simulations. The SoS approach advances life cycle stages including concept exploration, system design, engineering, training, and mission rehearsal. Component subsystems of the CM are described along with an explanation of input/output requirements. A notional implementation is described. Finally, applications to analysis and training, an evaluation of the CM based on recently proposed criteria found in the literature, and suggestions for future research are discussed.

show abstract

“…Thus, the purpose of the H-SIT is to protect against the uncovering of the core in order to ensure core safety. In this study, seal LOCA is no longer considered as a phenomenon in SBO because, in APR+, the standstill seal is applied to prevent seal LOCA (Darnowski et al, 2015).…”

Section: Analytical Study To Develop Optimum Operation Strategymentioning

confidence: 99%