EXPERIMENTAL STUDIES OF THERMOHYDRAULIC PROCESSES FOR THE PASSIVE HEAT-REMOVAL SYSTEM AT THE LENINGRADSKAYA NUCLEAR POWER PLANT

被引：0

作者：

Kukhtevich, V. O. ^{[1
]}

Bezlepkin, V. V. ^{[1
]}

Svetlov, S. V. ^{[1
]}

Sidorov, V. G. ^{[1
]}

Alekseev, S. B. ^{[1
]}

Balunov, B. F. ^{[2
]}

Shcheglov, A. A. ^{[2
]}

Ilyin, V. A. ^{[2
]}

Lyapin, N. V. ^{[2
]}

机构：

[1] Atomenergoproekt St Petersburg Res & Design Inst, St Petersburg, Russia

[2] Polzunov Sci Ind Assoc Res & Design Power Generat, St Petersburg, Russia

来源：

ATOMIC ENERGY | 2010年 / 108卷 / 05期

基金：

俄罗斯科学基金会;

关键词：

Industrial research - Steam generators - Nuclear energy - Steam power plants - Nuclear fuels;

D O I：

10.1007/s10512-010-9298-8

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 results of experimental studies of a passive system for removing heat through steam generators which were performed on a large-scale (1/110) stand at the Scientific-Industrial Association for Research and Design of Power-Generation Equipment (NPO TsKTI, St. Petersburg) are presented. The experiments show that the system performs reliably and effectively as designed. The experimental data were used to verify the thermohydraulic codes KORSAR and SOKRAT, which are used to model the thermohydraulic processes in the system at the Leningradskaya nuclear power plant.

引用

页码：335 / 342

页数：8

共 50 条

[21] Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant
Yan-Bin Liu
Xiang-Yu Meng
Xue-Sheng Wang
Qi-Ming Men
Yu-Yang Yuan
Jia-Ming Cao
NuclearScienceandTechniques, 2022, 33 (08) : 149 - 164
[22] Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant
Yan-Bin Liu
Xiang-Yu Meng
Xue-Sheng Wang
Qi-Ming Men
Yu-Yang Yuan
Jia-Ming Cao
Nuclear Science and Techniques, 2022, 33
[23] Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant
Liu, Yan-Bin
Meng, Xiang-Yu
Wang, Xue-Sheng
Men, Qi-Ming
Yuan, Yu-Yang
Cao, Jia-Ming
NUCLEAR SCIENCE AND TECHNIQUES, 2022, 33 (08)
[24] Computational and Experimental Validation of the Planned Emergency Heat-Removal System for BN-1200
D. G. Zaryugin
V. M. Poplavskii
V. I. Rachkov
A. P. Sorokin
Yu. E. Shvetsov
S. A. Rogozhkin
S. F. Shepelev
Atomic Energy, 2014, 116 : 271 - 277
[25] An Experimental Study of an Autonomous Heat Removal System Based on an Organic Rankine Cycle for an Advanced Nuclear Power Plant
Tauveron, Nicolas
Lhermet, Guillaume
Payebien, Benoit
Caney, Nadia
Morin, Franck
ENERGIES, 2024, 17 (20)
[26] Computational and Experimental Validation of the Planned Emergency Heat-Removal System for BN-1200
Zaryugin, D. G.
Poplavskii, V. M.
Rachkov, V. I.
Sorokin, A. P.
Shvetsov, Yu. E.
Rogozhkin, S. A.
Shepelev, S. F.
ATOMIC ENERGY, 2014, 116 (04) : 271 - 277
[27] A thermohydraulic code for low temperature nuclear heating reactor and its passive residual heat removal systems
Zhou, T
Su, GH
Jia, DN
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2004, 41 (12) : 1255 - 1270
[28] Experimental investigation on a passive injection and depressurization system for next generation of nuclear power plant
Barucca, L
Mansani, L
Saiu, G
PROCEEDINGS OF THE INTERNATIONAL TOPICAL MEETING ON ADVANCED REACTORS SAFETY, VOLS 1 AND 2, 1997, : 185 - 198
[29] Experimental study on transient flow characteristics in an equal-height-difference passive heat removal system for ocean nuclear power plants
Wang, Zhiwei
He, Yanping
Duan, Zhongdi
Huang, Chao
Liu, Shiwen
Xue, Hongxiang
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2023, 208
[30] RESEARCH ON THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF FLOATING NUCLEAR PLANTS
Wang Cong
Jue Wang
Hu Chen
Liao Yi
Chen Lei
PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 4, 2018,

← 1 2 3 4 5 →