Predication of the SMR Critical Core Performance Under Zero Power

Magy Kandil Salwa Helmy Ahmed Refaey

doi:doi:10.11648/j.ijse.20210501.13

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Predication of the SMR Critical Core Performance Under Zero Power

Magy Kandil Salwa Helmy Ahmed Refaey

Published in International Journal of Systems Engineering (Volume 5, Issue 1)

Received: 8 April 2021 Accepted: 26 April 2021 Published: 8 May 2021

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Abstract

In Nuclear Power plants, Reactivity Induced Accidents can lead to sever accidents. Rod Ejection Accidents are part of Reactivity Induced Accidents that induced through driven by reactivity insertion due to many failures. Thus, safety analysis of core behaviour under many external rod reactivities in Nuclear power plants are mandatory by regulators or safety authorities. In this research, a new dynamic model is proposed for core safety analysis under Rod Ejection Accidents. Thermal Power and other core parameters predictions are the most important goals for any reactor operation policy, during all periods and specifically at zero power to avoid severe accidents. The proposed model involves of a point kinetics explanation of neutronics combined with thermal hydraulic dynamics in the reactor core to predict its variation of parameters during transients using MATLAB environment. The proposed model is validated through comparing with the transient dynamic responses obtained through previous research for a chosen design of NuScale small modular reactor. In addition, the proposed model is verified through determining the dynamic reactor responses of Rod Ejection Accidents at hot zero power with many perturbations of different control rod ejection. The Performed safety analysis results of validation and the verification demonstrate that, the proposed model represents the reactor core behavior during the rod ejection transients with good prediction of thermal power of core peaks. Moreover, it allowed large explorations of core safety parameters and predicting the performance of its rector core during Rod Ejection Accidents under critical Hot zero power.

Published in	International Journal of Systems Engineering (Volume 5, Issue 1)
DOI	10.11648/j.ijse.20210501.13
Page(s)	18-24
Creative Commons	This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.
Copyright	Copyright © The Author(s), 2021. Published by Science Publishing Group

Keywords

A Pressured Water Smaller Rector, Reactivity Induced Accidents, A Rod Ejection Accident, Hot Zero Power, NuScale Small Modular Reactor

References

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[2]	Desquines J., et al., “The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)”, Journal of Nuclear Materials, 2011, 412: pp. 250-267. https://pennstate.pure.elsevier.com/en/publications/the-issue-of-stress-state-during-mechanical-tests-to-assess-cladd.
[3]	Magy M. Kandil, “Simulation of Pressurized Water Reactor under Specified Reactivity Accidents”, Journal of Multidisciplinary Engineering Science Studies (JMESS) ISSN: 2458-925XVol. 7 Issue 3, March -2021. http://www.jmess.org/wp-content/uploads/2021/03/JMESSP13420725.pdf.
[4]	Diamond D. J., et al., “Studies of the rod ejection accident in a PWR”, Technical reportW-6382, Brookhaven National Laboratory, Upton, NY, USA, 2002. https://www.nrc.gov/docs/ML0204/ML020430129.pdf.
[5]	Rodney A. Busquim E SILVA, “Implications of advanced computational methods for reactivity initiated accidents in nuclear reactors”, Ph. D, Sao Paulo, 2015. https://www.teses.usp.br/teses/disponiveis/3/3139/tde-20072016-142605/publico/RodneyAparecidoBusquimeSilva2015.pdf.
[6]	Cammi, A., Ponciroli, R., Borio di Tigliole, A., Magrotti, G., Prata, M., Chiesa, D., Previ-tali, E., 2013. A zero-dimensional model for simulation of TRIGA Mark II dynamic response. Prog. Nucl. Energy 68, 43–54.
[7]	Chang, M. H., Sim, S. K., Lee, D. J., 2000. SMART behavior under over-pressurizing accident conditions. Nucl. Eng. Des. 1991 (1), 187–196.
[8]	NuScale Plant Design Overview, NP-ER-0000-1198, Rev. 2, NuScale Power, LLC, Corvallis, Oregon, September 2013b., http://pbadupws.nrc.gov/docs/ML1326/ML13266A109.pdf230.
[9]	Chireuding Zeliang, Yi Mi, Akira Tokuhiro, Lixuan Lu and Aleksey Rezvoi, “Integral PWR-Type Small Modular Reactor Developmental Status, Design Characteristics and Passive Features: A Review”, Energies 2020, 13 (11), 2898; June 2020.https://doi.org/10.3390/en13112898.
[10]	Samet Egemen Arda, “Nonlinear Dynamic Modeling and Simulation of a Passively Cooled Small Modular Reactor”, PhD 2016. https://core.ac.uk/download/pdf/79587151.pdf.
[11]	Peter Rudling, Lars Olof Jernk, Friedrich Garzarolli, Ron Adamson “Nuclear Fuel Behaviour under RIA Conditions”, Advanced Nuclear Technology International, Sweden, December 2016. https://www.researchgate.net/profile/Peter-Rudling/publication/319065721_Nuclear_Fuel_Behaviour_under_RIA_Conditions_With_technical_contributions_from_IVIII_Disclaimer_IIVIII/links/598dc16aa6fdcc58acc06293/Nuclear-Fuel-Behaviour-under-RIA-Conditions-With-technical-contributions-from-IVIII-Disclaimer-IIVIII.pdf.
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[13]	Maria Aranzazu, “Fuel Failure Detection, Characterization and Modelling: Effecton Radionuclide Behaviour in PWR Primary Coolant”, Tigeras Menéndez, Ph. D, May 2009. http://oa.upm.es/3267/1/MARIA_ARANZAZU_TIGERAS_MENENDEZ.pdf.
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APA Style

Magy Kandil Salwa Helmy Ahmed Refaey. (2021). Predication of the SMR Critical Core Performance Under Zero Power. International Journal of Systems Engineering, 5(1), 18-24. https://doi.org/10.11648/j.ijse.20210501.13

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ACS Style

Magy Kandil Salwa Helmy Ahmed Refaey. Predication of the SMR Critical Core Performance Under Zero Power. Int. J. Syst. Eng. 2021, 5(1), 18-24. doi: 10.11648/j.ijse.20210501.13

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AMA Style

Magy Kandil Salwa Helmy Ahmed Refaey. Predication of the SMR Critical Core Performance Under Zero Power. Int J Syst Eng. 2021;5(1):18-24. doi: 10.11648/j.ijse.20210501.13

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@article{10.11648/j.ijse.20210501.13,
  author = {Magy Kandil Salwa Helmy Ahmed Refaey},
  title = {Predication of the SMR Critical Core Performance Under Zero Power},
  journal = {International Journal of Systems Engineering},
  volume = {5},
  number = {1},
  pages = {18-24},
  doi = {10.11648/j.ijse.20210501.13},
  url = {https://doi.org/10.11648/j.ijse.20210501.13},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijse.20210501.13},
  abstract = {In Nuclear Power plants, Reactivity Induced Accidents can lead to sever accidents. Rod Ejection Accidents are part of Reactivity Induced Accidents that induced through driven by reactivity insertion due to many failures. Thus, safety analysis of core behaviour under many external rod reactivities in Nuclear power plants are mandatory by regulators or safety authorities. In this research, a new dynamic model is proposed for core safety analysis under Rod Ejection Accidents. Thermal Power and other core parameters predictions are the most important goals for any reactor operation policy, during all periods and specifically at zero power to avoid severe accidents. The proposed model involves of a point kinetics explanation of neutronics combined with thermal hydraulic dynamics in the reactor core to predict its variation of parameters during transients using MATLAB environment. The proposed model is validated through comparing with the transient dynamic responses obtained through previous research for a chosen design of NuScale small modular reactor. In addition, the proposed model is verified through determining the dynamic reactor responses of Rod Ejection Accidents at hot zero power with many perturbations of different control rod ejection. The Performed safety analysis results of validation and the verification demonstrate that, the proposed model represents the reactor core behavior during the rod ejection transients with good prediction of thermal power of core peaks. Moreover, it allowed large explorations of core safety parameters and predicting the performance of its rector core during Rod Ejection Accidents under critical Hot zero power.},
 year = {2021}
}

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TY  - JOUR
T1  - Predication of the SMR Critical Core Performance Under Zero Power
AU  - Magy Kandil Salwa Helmy Ahmed Refaey
Y1  - 2021/05/08
PY  - 2021
N1  - https://doi.org/10.11648/j.ijse.20210501.13
DO  - 10.11648/j.ijse.20210501.13
T2  - International Journal of Systems Engineering
JF  - International Journal of Systems Engineering
JO  - International Journal of Systems Engineering
SP  - 18
EP  - 24
PB  - Science Publishing Group
SN  - 2640-4230
UR  - https://doi.org/10.11648/j.ijse.20210501.13
AB  - In Nuclear Power plants, Reactivity Induced Accidents can lead to sever accidents. Rod Ejection Accidents are part of Reactivity Induced Accidents that induced through driven by reactivity insertion due to many failures. Thus, safety analysis of core behaviour under many external rod reactivities in Nuclear power plants are mandatory by regulators or safety authorities. In this research, a new dynamic model is proposed for core safety analysis under Rod Ejection Accidents. Thermal Power and other core parameters predictions are the most important goals for any reactor operation policy, during all periods and specifically at zero power to avoid severe accidents. The proposed model involves of a point kinetics explanation of neutronics combined with thermal hydraulic dynamics in the reactor core to predict its variation of parameters during transients using MATLAB environment. The proposed model is validated through comparing with the transient dynamic responses obtained through previous research for a chosen design of NuScale small modular reactor. In addition, the proposed model is verified through determining the dynamic reactor responses of Rod Ejection Accidents at hot zero power with many perturbations of different control rod ejection. The Performed safety analysis results of validation and the verification demonstrate that, the proposed model represents the reactor core behavior during the rod ejection transients with good prediction of thermal power of core peaks. Moreover, it allowed large explorations of core safety parameters and predicting the performance of its rector core during Rod Ejection Accidents under critical Hot zero power.
VL  - 5
IS  - 1
ER  -

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Author Information

Magy Kandil Salwa Helmy Ahmed Refaey

Nuclear and Radiological Regulatory Authority (NRRA), Cairo, Egypt

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Plain Text BibTeX RIS

APA Style

Magy Kandil Salwa Helmy Ahmed Refaey. (2021). Predication of the SMR Critical Core Performance Under Zero Power. International Journal of Systems Engineering, 5(1), 18-24. https://doi.org/10.11648/j.ijse.20210501.13

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ACS Style

Magy Kandil Salwa Helmy Ahmed Refaey. Predication of the SMR Critical Core Performance Under Zero Power. Int. J. Syst. Eng. 2021, 5(1), 18-24. doi: 10.11648/j.ijse.20210501.13

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AMA Style

Magy Kandil Salwa Helmy Ahmed Refaey. Predication of the SMR Critical Core Performance Under Zero Power. Int J Syst Eng. 2021;5(1):18-24. doi: 10.11648/j.ijse.20210501.13

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@article{10.11648/j.ijse.20210501.13,
  author = {Magy Kandil Salwa Helmy Ahmed Refaey},
  title = {Predication of the SMR Critical Core Performance Under Zero Power},
  journal = {International Journal of Systems Engineering},
  volume = {5},
  number = {1},
  pages = {18-24},
  doi = {10.11648/j.ijse.20210501.13},
  url = {https://doi.org/10.11648/j.ijse.20210501.13},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijse.20210501.13},
  abstract = {In Nuclear Power plants, Reactivity Induced Accidents can lead to sever accidents. Rod Ejection Accidents are part of Reactivity Induced Accidents that induced through driven by reactivity insertion due to many failures. Thus, safety analysis of core behaviour under many external rod reactivities in Nuclear power plants are mandatory by regulators or safety authorities. In this research, a new dynamic model is proposed for core safety analysis under Rod Ejection Accidents. Thermal Power and other core parameters predictions are the most important goals for any reactor operation policy, during all periods and specifically at zero power to avoid severe accidents. The proposed model involves of a point kinetics explanation of neutronics combined with thermal hydraulic dynamics in the reactor core to predict its variation of parameters during transients using MATLAB environment. The proposed model is validated through comparing with the transient dynamic responses obtained through previous research for a chosen design of NuScale small modular reactor. In addition, the proposed model is verified through determining the dynamic reactor responses of Rod Ejection Accidents at hot zero power with many perturbations of different control rod ejection. The Performed safety analysis results of validation and the verification demonstrate that, the proposed model represents the reactor core behavior during the rod ejection transients with good prediction of thermal power of core peaks. Moreover, it allowed large explorations of core safety parameters and predicting the performance of its rector core during Rod Ejection Accidents under critical Hot zero power.},
 year = {2021}
}

Copy | Download

TY  - JOUR
T1  - Predication of the SMR Critical Core Performance Under Zero Power
AU  - Magy Kandil Salwa Helmy Ahmed Refaey
Y1  - 2021/05/08
PY  - 2021
N1  - https://doi.org/10.11648/j.ijse.20210501.13
DO  - 10.11648/j.ijse.20210501.13
T2  - International Journal of Systems Engineering
JF  - International Journal of Systems Engineering
JO  - International Journal of Systems Engineering
SP  - 18
EP  - 24
PB  - Science Publishing Group
SN  - 2640-4230
UR  - https://doi.org/10.11648/j.ijse.20210501.13
AB  - In Nuclear Power plants, Reactivity Induced Accidents can lead to sever accidents. Rod Ejection Accidents are part of Reactivity Induced Accidents that induced through driven by reactivity insertion due to many failures. Thus, safety analysis of core behaviour under many external rod reactivities in Nuclear power plants are mandatory by regulators or safety authorities. In this research, a new dynamic model is proposed for core safety analysis under Rod Ejection Accidents. Thermal Power and other core parameters predictions are the most important goals for any reactor operation policy, during all periods and specifically at zero power to avoid severe accidents. The proposed model involves of a point kinetics explanation of neutronics combined with thermal hydraulic dynamics in the reactor core to predict its variation of parameters during transients using MATLAB environment. The proposed model is validated through comparing with the transient dynamic responses obtained through previous research for a chosen design of NuScale small modular reactor. In addition, the proposed model is verified through determining the dynamic reactor responses of Rod Ejection Accidents at hot zero power with many perturbations of different control rod ejection. The Performed safety analysis results of validation and the verification demonstrate that, the proposed model represents the reactor core behavior during the rod ejection transients with good prediction of thermal power of core peaks. Moreover, it allowed large explorations of core safety parameters and predicting the performance of its rector core during Rod Ejection Accidents under critical Hot zero power.
VL  - 5
IS  - 1
ER  -

Copy | Download