scholarly journals Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code

2016 ◽  
Vol 2 ◽  
pp. 27
Author(s):  
Claudia Giovedi ◽  
Marco Cherubini ◽  
Alfredo Abe ◽  
Francesco D’Auria
Keyword(s):  
2019 ◽  
Vol 196 ◽  
pp. 00005 ◽  
Author(s):  
Eduard V. Usov ◽  
Pavel D. Lobanov ◽  
Ilya A. Klimonov ◽  
Alexander E. Kutlimetov ◽  
Anton A. Butov ◽  
...  

The paper contains the results of numerical simulation of stainless steel melt motions on the surface of uranium dioxide. The investigations are performed for purposes of understanding of the fuel rod behavior during the core disruptive accident in the fast reactors. The systems of mass, energy and momentum conservation equations are solved to simulate melt motion on the surface of the fuel pin. Heat transfer and friction between melt and pin's surface and melt and coolant flow are taken into consideration. The dependences of mass of the melt and the features of the melt motion on coolant velocity and contact angle between melt and surface of the fuel rod are presented.


2021 ◽  
Vol 7 (1) ◽  
pp. 7-16
Author(s):  
Stepan Lys ◽  

The paper describes the phenomenology of fuel rod behaviour in severe accident. As an example, an experiment is described resulting in severe damage of 19 fuel rod assembly of VVER type; it was carried out in the CORA facility in 1993 (Research Centre, Karlsruhe, Germany). Testing conditions and results of post-test investigations of fuel assembly are given. The fuel rod code RAPTA-SFD is briefly dealt with; the code was a participant in the International Standard Problem ISP-36. The basic results are presented acquired by computer modelling CORA-W2 experiment using RAPTA-SFD code. Among the presented experimentally acquired and calculated results, the scope of the data on stainless steel component behaviour is substantial. The tested CORA-W2 fuel assembly contained a significant quantity of steel components, viz., spacer grids, a guide thimble, and a cladding of an absorber element. It is to be borne in mind that the spacer grids and a guide thimble of the updated and upgraded fuel assembly of VVER-1000 are fabricated from Zr-alloy, hence, the relative quantitative characteristics of chemical interactions between materials and stainless steel (Cr-Ni alloy) will be much lower for the up-to-date upgraded fuel assembly under identical conditions.


Author(s):  
Shoji KATANISHI ◽  
Masahiko KYOYA ◽  
Kimio INOUE ◽  
Toshio FUJISHIRO ◽  
Masa-aki OCHIAI

2014 ◽  
Vol 8 (6) ◽  
Author(s):  
Alfredo Abe ◽  
Claudia Giovedi ◽  
Daniel de Souza Gomes ◽  
Antonio Teixeira e Silva

Author(s):  
Maolong Liu ◽  
Yuki Ishiwatari ◽  
Koji Okamoto

The SAMPSON code has been developed in the IMPACT project in Japan to investigate severe accident phenomena for light water reactors. It integrates various analysis modules into a single code. The authors improved the fuel rod heat-up module of SAMPSON code by modeling the oxidation reaction of various core structures, including Zircaloy, stainless steel and B4C. And the creep failures of the Zircaloy fuel cladding and stainless steel monitoring guide tubes of the source range monitor (SRM) in the reactor core was also modeled for severe accident analysis.


1965 ◽  
Vol 1 (5) ◽  
pp. 413-418 ◽  
Author(s):  
R. N. Duncan ◽  
W. H. Arlt ◽  
H. E. Williamson ◽  
C. J. Baroch ◽  
J. P. Hoffmann ◽  
...  
Keyword(s):  

Sign in / Sign up

Export Citation Format

Share Document