scholarly journals Investigating fission distribution behavior under various homogenization techniques for asymmetrical fuel assemblies and different reflector equivalence methods

2021 ◽  
Vol 157 ◽  
pp. 108221
Author(s):  
Kévin Fröhlicher ◽  
Vivian Salino ◽  
Alain Hébert
2010 ◽  
pp. 50-56
Author(s):  
Pablo R. Rubiolo ◽  
Guy Chaigne ◽  
Pierre Peturand ◽  
Jérôme Bigot ◽  
Jean-François Desseignes ◽  
...  

2019 ◽  
Vol 12 (4) ◽  
pp. 62-70
Author(s):  
K.N. Proskuryakov ◽  
A.V. Anikeev ◽  
E. Afshar ◽  
D.A. Pisareva
Keyword(s):  

Kerntechnik ◽  
2020 ◽  
Vol 85 (4) ◽  
pp. 213-225
Author(s):  
A. A. Gagarinskiy ◽  
Zh. Yu. Liventseva ◽  
D. R. Kireeva ◽  
D. A. Oleksyuk ◽  
Yu. P. Kalinin ◽  
...  
Keyword(s):  

Kerntechnik ◽  
2018 ◽  
Vol 83 (4) ◽  
pp. 307-313 ◽  
Author(s):  
A. Gagarinskiy ◽  
E. Osipova ◽  
Yu. Kalinin
Keyword(s):  

Materials ◽  
2021 ◽  
Vol 14 (8) ◽  
pp. 1818
Author(s):  
Di-Si Wang ◽  
Bo Liu ◽  
Sheng Yang ◽  
Bin Xi ◽  
Long Gu ◽  
...  

China is developing an ADS (Accelerator-Driven System) research device named the China initiative accelerator-driven system (CiADS). When performing a safety analysis of this new proposed design, the core behavior during the steam generator tube rupture (SGTR) accident has to be investigated. The purpose of our research in this paper is to investigate the impact from different heating conditions and inlet steam contents on steam bubble and coolant temperature distributions in ADS fuel assemblies during a postulated SGTR accident by performing necessary computational fluid dynamics (CFD) simulations. In this research, the open source CFD calculation software OpenFOAM, together with the two-phase VOF (Volume of Fluid) model were used to simulate the steam bubble behavior in heavy liquid metal flow. The model was validated with experimental results published in the open literature. Based on our simulation results, it can be noticed that steam bubbles will accumulate at the periphery region of fuel assemblies, and the maximum temperature in fuel assembly will not overwhelm its working limit during the postulated SGTR accident when the steam content at assembly inlet is less than 15%.


2019 ◽  
Vol 5 (3) ◽  
Author(s):  
Marcin Kopeć ◽  
Martina Malá

The ultrasonic (UT) measurements have a long history of utilization in the industry, also in the nuclear field. As the UT transducers are developing with the technology in their accuracy and radiation resistance, they could serve as a reliable tool for measurements of small but sensitive changes for the nuclear fuel assembly (FA) internals as the fuel rods are. The fuel rod bow is a phenomenon that may bring advanced problems as neglected or overseen. The quantification of this issue state and its probable progress may help to prevent the safety-related problems of nuclear reactors to occur—the excessive rod bow could, in the worst scenario, result in cladding disruption and then the release of actinides or even fuel particles to the coolant medium. Research Centre Rez has developed a tool, which could serve as a complementary system for standard postirradiation inspection programs for nuclear fuel assemblies. The system works in a contactless mode and reveals a 0.1 mm precision of measurements in both parallel (toward the probe) and perpendicular (sideways against the probe) directions.


Author(s):  
Zhixin Xu ◽  
Ming Wang ◽  
Binyan Song ◽  
WenYu Hou ◽  
Chao Wang

The Fukushima nuclear disaster has raised the importance on the reliability and risk research of the spent fuel pool (SFP), including the risk of internal events, fire, external hazards and so on. From a safety point of view, the low decay heat of the spent fuel assemblies and large water inventory in the SFP has made the accident progress goes very slow, but a large number of fuel assemblies are stored inside the spent fuel pool and without containment above the SFP building, it still has an unignored risk to the safety of the nuclear power plant. In this paper, a standardized approach for performing a holistic and comprehensive evaluation approach of the SFP risk based on the probabilistic safety analysis (PSA) method has been developed, including the Level 1 SFP PSA and Level 2 SFP PSA and external hazard PSA. The research scope of SFP PSA covers internal events, internal flooding, internal fires, external hazards and new risk source-fuel route risk is also included. The research will provide the risk insight of Spent Fuel Pool operation, and can help to make recommendation for the prevention and mitigation of SFP accidents which will be applicable for the SFP configuration risk management.


2004 ◽  
Vol 15 (3) ◽  
pp. 182-190
Author(s):  
Etsuro Shibata ◽  
Kazuhiro Fukuda ◽  
Takashi Nakamura ◽  
Takeshi Ari ◽  
Tomio Takasu ◽  
...  

1958 ◽  
Vol 3 (4) ◽  
pp. 395-402 ◽  
Author(s):  
J. Halperin ◽  
J. O. Blomeke ◽  
D. A. Mrkvicka

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