The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model

被引:11
作者
Duerigen, S. [1 ]
Rohde, U. [1 ]
Bilodid, Y. [1 ]
Mittag, S. [1 ]
机构
[1] Helmholtz Zentrum Dresden Rossendorf, D-01328 Dresden, Germany
关键词
FUNCTION EXPANSION; VERIFICATION; IMPLEMENTATION; SYSTEM; CORE; PWR;
D O I
10.3139/124.110382
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
The reactor dynamics code DYN3D is a three-dimensional best-estimate tool for simulating steady states and transients of light-water reactors and innovative reactor designs. An overview of the DYN3D features is provided. This paper further focuses on the recently developed trigonal-geometry diffusion model DYN3D-TRIDIF including a description of the underlying nodal approach and the characteristics of trigonal geometries. Via a mesh refinement study by means of a VVER-1000-type core benchmark using a fine-mesh diffusion reference solution, DYN3D-TRIDIF shows spatial convergence. Furthermore, the performance of DYN3D-TRIDIF is verified by means of a single-assembly problem on pin-cell level. Good agreement between DYN3D-TRIDIF and the detailed-geometry transport reference is achieved with an average deviation in power of less than 1 %.
引用
收藏
页码:310 / 318
页数:9
相关论文
共 39 条
[21]   Core response of a PWR to a slug of under-borated water [J].
Kliem, S ;
Rohde, U ;
Weiss, FP .
NUCLEAR ENGINEERING AND DESIGN, 2004, 230 (1-3) :121-132
[22]   Development of multi-physics code systems based on the reactor dynamics code DYN3D [J].
Kliem, S. ;
Gommlich, A. ;
Grahn, A. ;
Rohde, U. ;
Schuetze, J. ;
Frank, T. ;
Gomez, A. ;
Sanchez, V. .
KERNTECHNIK, 2011, 76 (03) :160-165
[23]   ATWS analysis for PWR using the coupled code system DYN3D/ATHLET [J].
Kliem, S. ;
Mittag, S. ;
Rohde, U. ;
Weiss, F. -P. .
ANNALS OF NUCLEAR ENERGY, 2009, 36 (08) :1230-1234
[24]  
Kochunas B, P PHYSOR 2010 ADV RE
[25]  
Koebke K, P TOP M REACT PHYS S
[26]  
Kozmenkov Y, ANN M GERM NUCL SOC
[27]   DYN3D-MSR spatial dynamics code for molten salt reactors [J].
Krepel, Jiri ;
Rohde, Ulrich ;
Grundmann, Ulrich ;
Weiss, Frank-Peter .
ANNALS OF NUCLEAR ENERGY, 2007, 34 (06) :449-462
[28]   TRANSURANUS - A FUEL-ROD ANALYSIS CODE READY FOR USE [J].
LASSMANN, K .
JOURNAL OF NUCLEAR MATERIALS, 1992, 188 :295-302
[29]  
Loetsch T, P 19 S AER VVER REAC
[30]   Modeling of flashing-induced instabilities in the start-up phase of natural-circulation BWRs using the two-phase flow code FLOCAL [J].
Manera, A ;
Rohde, U ;
Prasser, HM ;
van der Hagen, THJJ .
NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (14) :1517-1535