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

Citation
K. Kitoh et al., Refinement of transient criteria and safety analysis for a high-temperature reactor cooled by supercritical water, NUCL TECH, 135(3), 2001, pp. 252-264
Citations number
15
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR TECHNOLOGY
ISSN journal
00295450 → ACNP
Volume
135
Issue
3
Year of publication
2001
Pages
252 - 264
Database
ISI
SICI code
0029-5450(200109)135:3<252:ROTCAS>2.0.ZU;2-F
Abstract
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 fl ux ratio criterion where the deterioration heat flux is a junction of the c ore flow rate. Refinement of transient criteria related to the fuel rod des ign is undertaken, and new dominant transient criteria are proposed in whic h the cladding temperature is < 610 degreesC for Type 316 stainless steel a nd < 840 degreesC,for Inconel 700 to reduce the balance of the plant and im prove the thermal efficiency. The safety analysis for the high-temperature core using these new criteria is carried out. All the analyzed events satis fy, the new criteria. A new formula for the heat transfer correlation at su percritical pressure is proposed based on numerical simulation.