Steady-state Thermal-hydraulic Analysis of the TRIGA Plate Core Design by Using COOLOD-N2 and RELAP5 Codes

被引：1

作者：

Widodo, Surip ^{[1
]}

Hastuti, Endiah Puji ^{[1
]}

Alfa, Sudjatmi Kustituantini ^{[2
]}

Nazar, Reinaldy ^{[2
]}

机构：

[1] Ctr Nucl Reactor Technol & Safety, Puspiptek Area, Serpong 15310, Tangerang Selat, Indonesia

[2] Ctr Appl Nucl Sci & Technol, Jl Tamansari 71, Bandung 40132, Indonesia

来源：

3RD INTERNATIONAL CONFERENCE ON NUCLEAR ENERGY TECHNOLOGIES AND SCIENCES (ICONETS) 2019 | 2019年 / 2180卷

关键词：

STEADY-STATE; COOLOD-N2; RELAP5; TRIGA PLATE; DNB; SAFETY;

D O I：

10.1063/1.5135526

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：

The COOLOD-N2 and RELAP5 codes have been applied for a steady-state thermal-hydraulic safety analysis of the 2 MW TRIGA Plate core design at the BATAN, Indonesia. In order to get the best prediction, the maximum allowable axial node division was applied in COOLOD-N2 input model and the RELAP5 input nodalization was adjusted to match the COOLOD-N2 input model. The main objective of this research is to confirm the safety margins of different safety related parameter by steady-state calculation at full power level (2 MW). Therefore, we have calculated the coolant temperature, cladding surface temperature, fuel center temperature, departure from nucleate boiling ratio, and onset of nucleate boiling temperature profile across the hottest channel. The most significant conclusion is that all obtaining values indicate the reactor has enough safety margin.

引用

页数：8

共 30 条

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