The development of TRIAC-BATAN: a triso fuel performance analysis code

被引：1
|
作者：
Waskita, A. A. [1 ]
Setiadipura, T. [1 ]
机构：
[1] Natl Nucl Energy Agcy BATAN, Ctr Nucl Reactor Technol & Safety, Kawasan Puspiptek Serpon 15310, Tangerang, Indonesia
来源：
SYMPOSIUM OF EMERGING NUCLEAR TECHNOLOGY AND ENGINEERING NOVELTY (SENTEN 2018) | 2019年 / 1198卷
关键词：
computer code; fuel performance; triso coated particles; DESIGN;
D O I：
10.1088/1742-6596/1198/2/022035
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：
A computer code for analyzing the safety feature of triso coated particles for high temperature reactor has been developed based on PANAMA code. This python based code were separated into several modules to perform the main TRIAC-BATAN and linear interpolation calculation, to read the input data file, and to control the sequence of all TRIAC-BATAN calculation. In this initial development phase, TRIAC-BATAN can produce similar pattern as PANAMA calculation in the case of failure fraction of triso particles, either for Depressurized Loss Of Forced Cooling (DLOFC), 100 degrees C higher than DLOFC temperature and constant accident temperature at 1600 degrees C. By using the euclidean distance, TRIAC-BATAN calculation and PANAMA for DLOFC condition are separated in around 3.23.10(-7).
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收藏
页数：9
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