Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor

被引：1
|
作者：
Maraczy, Csaba [1 ]
Hegyi, Gyorgy [1 ]
Trosztel, Istvn [1 ]
Temesvari, Emese [1 ]
机构：
[1] Hungarian Acad Sci, Energy Res Ctr, POB 49, H-1525 Budapest 114, Hungary
来源：
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE | 2016年 / 2卷 / 01期
关键词：
fuel qualification test; supercritical water; research reactor; control rod withdrawal; coupled neutronic-thermohydraulic analysis;
D O I：
10.1115/1.4030933
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 aim of the supercritical water reactor-fuel qualification test (SCWR-FQT) Euratom-China collaborative project is to design an experimental facility for qualification of fuel for the supercritical water-cooled reactor. The facility is intended to be operated in the LVR-15 research reactor in the Czech Republic. The pressure tube of the FQT facility encloses four fuel rods that will operate in similar conditions to the evaporator of the HPLWR reactor. This article deals with the three-dimensional (3D) coupled neutronic-thermohydraulic steady-state and transient analysis of LVR-15 with the fueled loop. Conservatively calculated enveloping parameters (e.g., reactivity coefficients) were determined for the safety analysis. The control rod withdrawal analysis of the FQT facility with and without reactor SCRAM was carried out with the KIKO3D-ATHLET-coupled dynamic code.
引用
收藏
页数：5
相关论文
共 50 条
  • [41] Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor
    Kostal, Michal
    Matej, Zdenek
    Mravec, Filip
    Cvachovec, Frantisek
    Schulc, Martin
    Juricek, Vlastimil
    Rypar, Vojtech
    Soltes, Jaroslav
    Losa, Evzen
    Viererbl, Ladislav
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2019, 5 (03):
  • [42] Numerical analysis on inlet and outlet sections of a test fuel assembly for a Supercritical Water Reactor
    Kiss, Attila
    Vago, Tamas
    Aszodi, Attila
    NUCLEAR ENGINEERING AND DESIGN, 2015, 295 : 415 - 428
  • [43] CRITICAL EXPERIMENTS WITH CONCRETE-REFLECTED FAST TEST REACTOR-FUEL PINS IN WATER
    BIERMAN, SR
    DURST, BM
    CLAYTON, ED
    HOWES, BW
    NUCLEAR TECHNOLOGY, 1980, 49 (01) : 40 - 46
  • [44] Characteristics analysis of MOX fuel in supercritical water cooled reactor
    Sun, Can-Hui
    Zhou, Tao
    Li, Zhen-Yang
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2010, 44 (SUPPL. 1): : 346 - 351
  • [45] EXPERIMENTAL RESEARCH OF THE PROCESS OF REACTOR-FUEL WATER-COOLING UNDER NONNOMINAL CONDITIONS
    HERMANSKY, B
    JADERNA ENERGIE, 1983, 29 (02): : 63 - 68
  • [46] Control rod performance in Siemens pressurized water reactor fuel assemblies
    Endrizzi, I
    ANNUAL MEETING ON NUCLEAR TECHNOLOGY '97, 1997, : 407 - 410
  • [47] Interpretation of the Control Rod Withdrawal Test in the Sodium-Cooled Fast Reactor Phenix
    Pascal, V.
    Prulhiere, G.
    Vanier, M.
    Fontaine, B.
    NUCLEAR SCIENCE AND ENGINEERING, 2013, 175 (02) : 109 - 123
  • [48] Abnormal control rod withdrawal analysis for innovative research reactor using PARET-ANL codes
    Hastuti, E. P.
    Tukiran, S.
    Widodo, S.
    Sudarmono
    KERNTECHNIK, 2018, 83 (02) : 96 - 105
  • [49] FINAL FUEL PIN ENRICHMENT AND CONTROL ROD LOADINGS FOR FAST TEST REACTOR
    RAMCHANDRAN, S
    CALAMAI, GJ
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1973, 16 (JUN): : 278 - 279
  • [50] In-pile testing of ITER first wall mock-ups at relevant thermal loading conditions in the LVR-15 nuclear research reactor
    Kysela, Jan
    Entler, Slavomir
    Vsolak, Rudolf
    Klabik, Tomas
    Zlamal, Ondrej
    Bellin, Boris
    Zacchia, Francesco
    FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1271 - 1275
12345