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

被引：0

作者：

Liao H. ^{[1
]}

Li C. ^{[1
]}

He Y. ^{[1
]}

Wu Y. ^{[1
]}

Zhang Y. ^{[1
]}

Tian W. ^{[1
]}

Su G.H. ^{[1
]}

Qiu S. ^{[1
]}

机构：

[1] School of Nuclear Science and Technology, Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an

来源：

International Journal of Advanced Nuclear Reactor Design and Technology | 2021年 / 3卷

关键词：

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

D O I：

10.1016/j.jandt.2021.06.003

中图分类号：

学科分类号：

摘要：

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. © 2021 Xi'an Jiaotong University

引用

页码：54 / 65

页数：11

共 50 条

[21] SAMPLE CALCULATIONS ON FUEL ROD BEHAVIOR DURING A LOCA WITH CODE SYSTEM SSYST-MOD-1
MEYDER, R
RAFF, S
SENGPIEL, W
NUCLEAR ENGINEERING AND DESIGN, 1977, 43 (02) : 455 - 462
[22] HYPOTHETICAL PWR LOCA SENSITIVITY TO FUEL ROD MATERIAL PROPERTIES
FALOTICO, RN
OEHLBERG, RN
HAGRMAN, DL
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 30 (NOV): : 390 - 391
[23] Evaluation of the FRANCO Finite Element Fuel Rod ANalysis COde
Pennsylvania State Univ, University Park, United States
Ann Nucl Energy, 7 (553-565):
[24] MECHANICAL ANALYSIS OF THE FUEL ROD WITH THE KWU CODE SENATOR.
Hering, W.
Res Mechanica: International Journal of Structural Mechanics and Materials Science, 1986, 18 (03): : 191 - 200
[25] MECHANICAL ANALYSIS OF THE FUEL-ROD WITH THE KWU CODE SENATOR
HERING, W
RES MECHANICA, 1986, 18 (03): : 191 - 200
[26] TRANSURANUS - A FUEL-ROD ANALYSIS CODE READY FOR USE
LASSMANN, K
JOURNAL OF NUCLEAR MATERIALS, 1992, 188 : 295 - 302
[27] Valuation of the FRANCO Finite Element Fuel Rod Analysis Code
Feltus, MA
Lee, KG
ANNALS OF NUCLEAR ENERGY, 1996, 23 (07) : 553 - 565
[28] SPEAR CODE SYSTEM - LWR FUEL ROD MECHANICAL PERFORMANCE PREDICTOR
CHRISTENSEN, R
ROHRER, R
TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1978, 30 (NOV): : 172 - 173
[29] Analysis of Fuel Rod Behavior Under Steady State and Transient Condition by Modification of THEATRe Code
Nawaz, Amjad
Yoshikawa, Hidekazu
Yang, Ming
Hussain, Anwar
PROCEEDINGS OF THE 20TH PACIFIC BASIN NUCLEAR CONFERENCE, VOL 1, 2017, : 151 - 162
[30] Extension of the TRANSURANUS code to the fuel rod performance analysis of LBE-cooled nuclear reactors
Botazzoli, P.
Agosti, F.
Di Marcello, V.
Luzzi, L.
RADIATION EFFECTS AND DEFECTS IN SOLIDS, 2009, 164 (5-6): : 330 - 335

← 1 2 3 4 5 →