THERMAL HYDRAULIC CALCULATIONS OF THE IRT-SOFIA RESEARCH REACTOR WITH LEU FUEL IRT-4M, SOFIA

被引：0
|
作者：
Kadalev, Stoyan [1 ]
机构：
[1] Bulgarian Acad Sci, Inst Nucl Res & Nucl Energy, BU-1784 Sofia, Bulgaria
来源：
COMPTES RENDUS DE L ACADEMIE BULGARE DES SCIENCES | 2012年 / 65卷 / 09期
关键词：
thermal-hydraulic calculations; IRT-Sofia reactor; IRT-4M LEU fuel; PRESSURE-DROP; HEAT-TRANSFER;
D O I：
暂无
中图分类号：
O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];
学科分类号：
07 ; 0710 ; 09 ;
摘要：
The neutronic calculations of the IRT-Sofia research reactor with fuel assemblies (FA) of the IRT-4M type, containing low enriched uranium (19.75%), confirmed the justness of the selection of its initial core configuration. On the basis of the neutronic calculation results the thermal-hydraulic calculations were done by PLTEMP code. Three possible operational regimes have been considered. For each of them the margin coefficients of the water onset of the nucleate boiling (ONB) have been determined. An analysis has been made on the fuel element surface for the particular fuel assembly with maximum power density. The calculations have been accomplished for the core water inlet temperature of 45 degrees C. The results are in compliance with the thermal-hydraulic safety requirements. This is valid for all analyzed regimes.
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页码：1185 / 1192
页数：8
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