Refinement of transient criteria and safety analysis for a high-temperature reactor cooled by supercritical water

被引：43

作者：

Kitoh, K ^{[1
]}

Koshizuka, S ^{[1
]}

Oka, Y ^{[1
]}

机构：

[1] Univ Tokyo, Nucl Engn Res Lab, Tokai, Ibaraki 3191106, Japan

来源：

NUCLEAR TECHNOLOGY | 2001年 / 135卷 / 03期

关键词：

D O I：

10.13182/NT01-A3220

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 [核科学与技术]; 082701 [核能科学与工程];

摘要：

In past designs of supercritical water-cooled reactors, the core flow rate has had to be kept high enough to satisfy the minimum deterioration heat flux ratio criterion where the deterioration heat flux is a junction of the core flow rate. Refinement of transient criteria related to the fuel rod design is undertaken, and new dominant transient criteria are proposed in which the cladding temperature is < 610 degreesC for Type 316 stainless steel and < 840 degreesC,for Inconel 700 to reduce the balance of the plant and improve the thermal efficiency. The safety analysis for the high-temperature core using these new criteria is carried out. All the analyzed events satisfy, the new criteria. A new formula for the heat transfer correlation at supercritical pressure is proposed based on numerical simulation.

引用

页码：252 / 264

页数：13

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