Simulations of RUTA-70 reactor with CERMET fuel using DYN3D/ATHLET and DYN3D/RELAP5 coupled codes

被引：2

作者：

Kozmenkov, Y. ^{[1
]}

Rohde, U. ^{[1
]}

Baranaev, Y. ^{[2
]}

Glebov, A. ^{[2
]}

机构：

[1] HZDR, D-01328 Dresden, Germany

[2] Russian Federat Inst Phys & Power Engn, State Sci Ctr, Obninsk 249020, Russia

来源：

KERNTECHNIK | 2012年 / 77卷 / 04期

关键词：

D O I：

10.3139/124.110250

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

RUTA-70 model for simulations with the internally coupled codes DYN3D/ATHLET and DYN3D/RELAP5 was developed. A 3-D power distribution in the core is calculated by DYN3D with thermal-hydraulic feedback from the system codes. A steady-state corresponding to the full reactor power and at accident scenario initiated by failure of all primary codes pumps were simulated with the DYN3D/ATHLET and LYN3D/RELAP5 coupled code systems to verify these codes. The compared coupled codes give close predictions for the initial and final states of the simulated accident but not for the transition between them. The observed deviations are explained by differences in the subcooled boiling models of the employed versions of ATHLET and RELAP5. Nevertheless., both simulations confirm a high level of the reactor inherent safety. The allowed safety margins were not reached.

引用

页码：249 / 257

页数：9

共 16 条

[1] Adamov E. O., 1998, IAEATECDOC1056
[2] [Anonymous], 2001, NUREGCR5535REV1, VI
[3] [Anonymous], 2004, FUEL REV FUEL DES DA
[4] [Anonymous], 2009, ATHLET MOD 2 2 CYCL
[5] Austregesilo H., 2006, ATHLET MOD 2 1 CYCLE, V4
[6] Austregesilo H., 2009, ATHLET MOD 2 2 CYCLE, V4
[7] CORRELATION FOR BOILING HEAT TRANSFER TO SATURATED FLUIDS IN CONVECTIVE FLOW
CHEN, JC
[J]. INDUSTRIAL & ENGINEERING CHEMISTRY PROCESS DESIGN AND DEVELOPMENT, 1966, 5 (03): : 322 - &
[8] Grundmann U., 1995, Proceedings of the International Conference, Mathematics and Computations, Reactor Physics, and Environmental Analyses, P257
[9] Grundmann U., 2000, P 2000 ANS INT TOP M
[10] Modelling of void formation in the subcooled boiling regime in the ATHLET code to simulate flow instability for research reactors
Hainoun, A
Hicken, E
Wolters, J
[J]. NUCLEAR ENGINEERING AND DESIGN, 1996, 167 (02) : 175 - 191

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