ASSESSMENT OF THERMAL-HYDRAULIC CHARACTERISTICS OF THE PRIMARY CIRCUIT

被引：7

作者：

FRANCOIS, G

AZARIAN, G

ASTEGIANO, JC

LACROIX, C

POET, G

机构：

[1] CEN CADARACHE,COMMISSARIAT ENERGIE ATOM,DEPT RECH PHYS,F-13108 ST PAUL DURANCE,FRANCE

[2] ELECT FRANCE,NATL HYDRAUL LAB,F-92141 CLAMART,FRANCE

[3] ELECT FRANCE,F-69611 VILLEURBANNE,FRANCE

来源：

NUCLEAR SCIENCE AND ENGINEERING | 1990年 / 106卷 / 01期

关键词：

Superphenix - Thermal Hydraulics;

D O I：

10.13182/NSE90-A23757

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：

Thermal-hydraulic studies are presented of the primary circuit performed in a large number of water mock-ups in relation to physical problems that occurred during the commissioning of Superphenix. Mock-up results and numerical model predictions are compared with reactor measurements in steady-state or in transient conditions.

引用

页码：55 / 63

页数：9