Analysis of the influence of different heat transfer correlations for HTR helical coil tube bundle steam generators with the system code TRACE

被引：5

作者：

Esch, Markus ^{[1
,2
]}

Hurtado, Antonio ^{[1
]}

Knoche, Dietrich ^{[2
]}

Tietsch, Wolfgang ^{[2
]}

机构：

[1] Tech Univ Dresden, D-01069 Dresden, Germany

[2] Westinghouse Elect Germany GmbH, D-68167 Mannheim, Germany

来源：

NUCLEAR ENGINEERING AND DESIGN | 2012年 / 251卷

关键词：

D O I：

10.1016/j.nucengdes.2011.09.056

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：

For next high temperature reactor projects, e.g. for electricity production or nuclear process heat applications, the steam generator is a crucial component. The typical design consists of a helical coil tube bundle steam generator with several tubes in different tube cylinders connected in parallel. This type of steam generator was a significant component used in the THTR-300. The influence of different heat transfer correlations for the primary side on the steam outlet temperature is being analyzed by the nodal thermal hydraulics code TRACE for the THTR-300 steam generator and compared to experimental data. The results of the standard TRACE code are compared to results with modified Nusselt numbers for the primary side and they will be elaborated in this paper. These modified Nusselt numbers were used for the heat transfer calculations of the THTR-300 steam generator design. (C) 2011 Elsevier B.V. All rights reserved.

引用

页码：374 / 380

页数：7

共 10 条

[1]

Bajorek S., 2008, TRACE V5 0 USERS MAN

[2]

Bajorek S., 2008, TRACE V5. 0 Theory manual, field equations, solution methods and physical models

[3]

Esch M., 2003, P HTR 2008 WASH DC U

[4]

Jurgens B., 1987, TEMPERATURMESSUNG DE

[5]

Odar F., 2004, TRACE V4 0 USERS MAN

[6]

Reactor Core Design for High Temperature Gas-Cooled Reactors, 1978, 31021 KTA

[7]

SNAP, 2008, SNAP US MAN

[8]

Sulzer, 1973, HAUPT MAT TEMP INT D

[9]

Sulzer, TA1395 SULZ

[10]

Thieme M., 2008, JAHR KERNT HAMB GERM

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