The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview

D. P. Weber; T. Sofu; P. A. Pfeiffer; W. S. Yang; T. A. Taiwo; H. G. Joo; J. Y. Cho; K. S. Kim; T. H. Chun; T. J. Downar; J. W. Thomas; Z. Zhong; C. H. Kim; B. S. Han

The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview

D. P. Weber, T. Sofu, P. A. Pfeiffer, W. S. Yang, T. A. Taiwo, H. G. Joo, J. Y. Cho, K. S. Kim, T. H. Chun, T. J. Downar, J. W. Thomas, Z. Zhong, C. H. Kim, B. S. Han

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

14 Scopus citations

Abstract

As part of a US-ROK collaborative I-NERI project, a comprehensive high fidelity reactor core modeling capability is being developed for detailed analysis of current and advanced reactor designs. The work involves the coupling of advanced numerical models such as computational fluid dynamics (CFD) for thermal hydraulic calculations, whole core discrete integral transport for neutronics calculations, and thermo-mechanical techniques for structural calculations. The product code has been designed to run on parallel high performance computers. This integrated simulation capability will provide a verifiable computational tool to perform intensive studies on the operational and safety characteristics of various design alternatives and to compare the results obtained with presently available tools to those from this high fidelity capability. This paper provides an overview of the project and a summary of the key elements of the integrated code.

Original language	English
Title of host publication	Proceedings of the PHYSOR 2004
Subtitle of host publication	The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Pages	13-20
Number of pages	8
State	Published - 2004
Event	PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments - Chicago, IL, United States Duration: Apr 25 2004 → Apr 29 2004

Publication series

Name	Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Conference

Conference	PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Country/Territory	United States
City	Chicago, IL
Period	04/25/04 → 04/29/04

Keywords

CFD
Computational fluid dynamics
Core analysis
Coupled codes
High performance computing
Integral transport theory
Neutronics
Numerical reactor
Parallel computers
Reactor physics
Thermal-hydraulics

Cite this

Weber, D. P., Sofu, T., Pfeiffer, P. A., Yang, W. S., Taiwo, T. A., Joo, H. G., Cho, J. Y., Kim, K. S., Chun, T. H., Downar, T. J., Thomas, J. W., Zhong, Z., Kim, C. H., & Han, B. S. (2004). The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview. In Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments (pp. 13-20). (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

Weber, D. P. ; Sofu, T. ; Pfeiffer, P. A. et al. / The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview. Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2004. pp. 13-20 (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

@inproceedings{ef72aa45198c4c8090e2aaadd8eb7239,

title = "The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview",

abstract = "As part of a US-ROK collaborative I-NERI project, a comprehensive high fidelity reactor core modeling capability is being developed for detailed analysis of current and advanced reactor designs. The work involves the coupling of advanced numerical models such as computational fluid dynamics (CFD) for thermal hydraulic calculations, whole core discrete integral transport for neutronics calculations, and thermo-mechanical techniques for structural calculations. The product code has been designed to run on parallel high performance computers. This integrated simulation capability will provide a verifiable computational tool to perform intensive studies on the operational and safety characteristics of various design alternatives and to compare the results obtained with presently available tools to those from this high fidelity capability. This paper provides an overview of the project and a summary of the key elements of the integrated code.",

keywords = "CFD, Computational fluid dynamics, Core analysis, Coupled codes, High performance computing, Integral transport theory, Neutronics, Numerical reactor, Parallel computers, Reactor physics, Thermal-hydraulics",

author = "Weber, \{D. P.\} and T. Sofu and Pfeiffer, \{P. A.\} and Yang, \{W. S.\} and Taiwo, \{T. A.\} and Joo, \{H. G.\} and Cho, \{J. Y.\} and Kim, \{K. S.\} and Chun, \{T. H.\} and Downar, \{T. J.\} and Thomas, \{J. W.\} and Z. Zhong and Kim, \{C. H.\} and Han, \{B. S.\}",

year = "2004",

language = "English",

isbn = "0894486837",

series = "Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments",

pages = "13--20",

booktitle = "Proceedings of the PHYSOR 2004",

note = "PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments ; Conference date: 25-04-2004 Through 29-04-2004",

}

Weber, DP, Sofu, T, Pfeiffer, PA, Yang, WS, Taiwo, TA, Joo, HG, Cho, JY, Kim, KS, Chun, TH, Downar, TJ, Thomas, JW, Zhong, Z, Kim, CH & Han, BS 2004, The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview. in Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, pp. 13-20, PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments, Chicago, IL, United States, 04/25/04.

The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview. / Weber, D. P.; Sofu, T.; Pfeiffer, P. A. et al.
Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2004. p. 13-20 (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview

AU - Weber, D. P.

AU - Sofu, T.

AU - Pfeiffer, P. A.

AU - Yang, W. S.

AU - Taiwo, T. A.

AU - Joo, H. G.

AU - Cho, J. Y.

AU - Kim, K. S.

AU - Chun, T. H.

AU - Downar, T. J.

AU - Thomas, J. W.

AU - Zhong, Z.

AU - Kim, C. H.

AU - Han, B. S.

PY - 2004

Y1 - 2004

N2 - As part of a US-ROK collaborative I-NERI project, a comprehensive high fidelity reactor core modeling capability is being developed for detailed analysis of current and advanced reactor designs. The work involves the coupling of advanced numerical models such as computational fluid dynamics (CFD) for thermal hydraulic calculations, whole core discrete integral transport for neutronics calculations, and thermo-mechanical techniques for structural calculations. The product code has been designed to run on parallel high performance computers. This integrated simulation capability will provide a verifiable computational tool to perform intensive studies on the operational and safety characteristics of various design alternatives and to compare the results obtained with presently available tools to those from this high fidelity capability. This paper provides an overview of the project and a summary of the key elements of the integrated code.

AB - As part of a US-ROK collaborative I-NERI project, a comprehensive high fidelity reactor core modeling capability is being developed for detailed analysis of current and advanced reactor designs. The work involves the coupling of advanced numerical models such as computational fluid dynamics (CFD) for thermal hydraulic calculations, whole core discrete integral transport for neutronics calculations, and thermo-mechanical techniques for structural calculations. The product code has been designed to run on parallel high performance computers. This integrated simulation capability will provide a verifiable computational tool to perform intensive studies on the operational and safety characteristics of various design alternatives and to compare the results obtained with presently available tools to those from this high fidelity capability. This paper provides an overview of the project and a summary of the key elements of the integrated code.

KW - CFD

KW - Computational fluid dynamics

KW - Core analysis

KW - Coupled codes

KW - High performance computing

KW - Integral transport theory

KW - Neutronics

KW - Numerical reactor

KW - Parallel computers

KW - Reactor physics

KW - Thermal-hydraulics

UR - https://www.scopus.com/pages/publications/22344449428

M3 - Conference contribution

AN - SCOPUS:22344449428

SN - 0894486837

SN - 9780894486838

T3 - Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

SP - 13

EP - 20

BT - Proceedings of the PHYSOR 2004

T2 - PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Y2 - 25 April 2004 through 29 April 2004

ER -

Weber DP, Sofu T, Pfeiffer PA, Yang WS, Taiwo TA, Joo HG et al. The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview. In Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments. 2004. p. 13-20. (Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments).

The numerical nuclear reactor for high fidelity integrated simulation of neutronic, thermal-hydraulic and thermo mechanical phenomena - Project overview

Abstract

Publication series

Conference

Keywords

Other files and links

Fingerprint

Cite this