Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code

Haoyu Liao; Chenxi Li; Yanan He; Yingwei Wu; Yapei Zhang; Wenxi Tian; G. H. Su; Suizheng Qiu

doi:10.1016/j.jandt.2021.06.003

Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code

Haoyu Liao
, Chenxi Li
, Yanan He
, Yingwei Wu
, Yapei Zhang
, Wenxi Tian
, G. H. Su
, Suizheng Qiu

School of Energy and Power Engineering

Xi'an Jiaotong University

Research output: Contribution to journal › Article › peer-review

4 Scopus citations

Abstract

Loss of Coolant Accident (LOCA) is one of the major design-basis accidents in LWRs. Fuel rod may fail due to the rupture of the cladding. By developing a LOCA simulation module, the steady-state fuel rod performance analysis code, FROBA-ROD, is now capable to predict fuel rod behaviors under a LOCA transient. The relevant models and the code was verified and validated by comparing with authoritative commercial codes and with the experimental measurements. Comprehensive calculations and analyses of fuel rod behaviors under different LOCA transients were performed by the new version of FROBA-ROD. Compared the failure conditions to the non-failure conditions through the simulation results, a cladding failure threshold equation was found for a better estimate of the integrity of high burnup fuel rods under LOCA transients.

Original language	English
Pages (from-to)	54-65
Number of pages	12
Journal	International Journal of Advanced Nuclear Reactor Design and Technology
Volume	3
DOIs	https://doi.org/10.1016/j.jandt.2021.06.003
State	Published - Jan 2021

Keywords

Cladding failure
Cladding oxidation
FROBA-ROD
Failure threshold
High-temperature creep
Loss of coolant accident

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10.1016/j.jandt.2021.06.003

Cite this

@article{226dd524f1714b7aa39aed82bf545b13,

title = "Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code",

abstract = "Loss of Coolant Accident (LOCA) is one of the major design-basis accidents in LWRs. Fuel rod may fail due to the rupture of the cladding. By developing a LOCA simulation module, the steady-state fuel rod performance analysis code, FROBA-ROD, is now capable to predict fuel rod behaviors under a LOCA transient. The relevant models and the code was verified and validated by comparing with authoritative commercial codes and with the experimental measurements. Comprehensive calculations and analyses of fuel rod behaviors under different LOCA transients were performed by the new version of FROBA-ROD. Compared the failure conditions to the non-failure conditions through the simulation results, a cladding failure threshold equation was found for a better estimate of the integrity of high burnup fuel rods under LOCA transients.",

keywords = "Cladding failure, Cladding oxidation, FROBA-ROD, Failure threshold, High-temperature creep, Loss of coolant accident",

author = "Haoyu Liao and Chenxi Li and Yanan He and Yingwei Wu and Yapei Zhang and Wenxi Tian and Su, \{G. H.\} and Suizheng Qiu",

note = "Publisher Copyright: {\textcopyright} 2021 Xi'an Jiaotong University",

year = "2021",

month = jan,

doi = "10.1016/j.jandt.2021.06.003",

language = "英语",

volume = "3",

pages = "54--65",

journal = "International Journal of Advanced Nuclear Reactor Design and Technology",

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}

TY - JOUR

T1 - Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code

AU - Liao, Haoyu

AU - Li, Chenxi

AU - He, Yanan

AU - Wu, Yingwei

AU - Zhang, Yapei

AU - Tian, Wenxi

AU - Su, G. H.

AU - Qiu, Suizheng

PY - 2021/1

Y1 - 2021/1

N2 - Loss of Coolant Accident (LOCA) is one of the major design-basis accidents in LWRs. Fuel rod may fail due to the rupture of the cladding. By developing a LOCA simulation module, the steady-state fuel rod performance analysis code, FROBA-ROD, is now capable to predict fuel rod behaviors under a LOCA transient. The relevant models and the code was verified and validated by comparing with authoritative commercial codes and with the experimental measurements. Comprehensive calculations and analyses of fuel rod behaviors under different LOCA transients were performed by the new version of FROBA-ROD. Compared the failure conditions to the non-failure conditions through the simulation results, a cladding failure threshold equation was found for a better estimate of the integrity of high burnup fuel rods under LOCA transients.

AB - Loss of Coolant Accident (LOCA) is one of the major design-basis accidents in LWRs. Fuel rod may fail due to the rupture of the cladding. By developing a LOCA simulation module, the steady-state fuel rod performance analysis code, FROBA-ROD, is now capable to predict fuel rod behaviors under a LOCA transient. The relevant models and the code was verified and validated by comparing with authoritative commercial codes and with the experimental measurements. Comprehensive calculations and analyses of fuel rod behaviors under different LOCA transients were performed by the new version of FROBA-ROD. Compared the failure conditions to the non-failure conditions through the simulation results, a cladding failure threshold equation was found for a better estimate of the integrity of high burnup fuel rods under LOCA transients.

KW - Cladding failure

KW - Cladding oxidation

KW - FROBA-ROD

KW - Failure threshold

KW - High-temperature creep

KW - Loss of coolant accident

UR - https://www.scopus.com/pages/publications/85138445219

U2 - 10.1016/j.jandt.2021.06.003

DO - 10.1016/j.jandt.2021.06.003

M3 - 文章

AN - SCOPUS:85138445219

SN - 2468-6050

VL - 3

SP - 54

EP - 65

JO - International Journal of Advanced Nuclear Reactor Design and Technology

JF - International Journal of Advanced Nuclear Reactor Design and Technology

ER -

Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code

Abstract

Keywords

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