scholarly journals Irradiation performance of experimental fast reactor "JOYO" MK-I driver fuel assemblies.

1985 ◽  
Vol 27 (5) ◽  
pp. 435-449 ◽  
Author(s):  
Toshiyuki ITAKI ◽  
Keiichi KONO ◽  
Hirokatsu TACHI ◽  
Sadamu YAMANOUCHI ◽  
Shunichi YUHARA ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Fuel Assemblies ◽  
Irradiation Performance

Calculation studies of coated particles performance in sodium-cooled fast reactor

Kerntechnik ◽  
2021 ◽  
Vol 86 (1) ◽  
pp. 45-49
Author(s):  
N. V. Maslov ◽  
E. I. Grishanin ◽  
P. N. Alekseev
Keyword(s):  
Fast Reactor ◽  
Reactor Core ◽  
Heat Removal ◽  
Design Solution ◽  
Fast Neutrons ◽  
Steel Shell ◽  
Primary Circuit ◽  
Coated Particles ◽  
The Core ◽  
Fuel Assemblies

Abstract This paper presents results of calculation studies of the viability of coated particles in the conditions of the reactor core on fast neutrons with sodium cooling, justifying the development of the concept of the reactor BN with microspherical fuel. Traditional rod fuel assemblies with pellet MOX fuel in the core of a fast sodium reactor are directly replaced by fuel assemblies with micro-spherical mixed (U,Pu)C-fuel. Due to the fact that the micro-spherical (U, Pu)C fuel has a developed heat removal surface and that the design solution for the fuel assembly with coated particles is horizontal cooling of the microspherical fuel, the core has additional possibilities of increasing inherent (passive) safety and improve the competitiveness of BN type of reactors. It is obvious from obtained results that the microspherical (U, Pu)C fuel is limited with the maximal burn-up depth of ∼11% of heavy atoms in conditions of the sodium-cooled fast reactor core at the conservative approach; it gives the possibility of reaching stated thermal-hydraulic and neutron-physical characteristics. Such a tolerant fuel makes it less likely that fission products will enter the primary circuit in case of accidents with loss of coolant and the introduction of positive reactivity, since the coating of microspherical fuel withstands higher temperatures than the steel shell of traditional rod-type fuel elements.

scholarly journals Study of Innovative Chemical Processes for Sodium Fast Reactor Fuel Assemblies Cleaning

2012 ◽  
Vol 7 ◽  
pp. 84-91
Author(s):  
M. Lacroix ◽  
N. Simon ◽  
C. Perrais ◽  
J.P. Simonin ◽  
S. Trambaud
Keyword(s):  
Fast Reactor ◽  
Chemical Processes ◽  
Reactor Fuel ◽  
Sodium Fast Reactor ◽  
Fuel Assemblies ◽  
Fast Reactor Fuel

A High-Breeding Fast Reactor with Fission Product Gas Purge/Tube-in-Shell Metallic Fuel Assemblies

1991 ◽  
Vol 93 (3) ◽  
pp. 305-329 ◽  
Author(s):  
Toru Hiraoka ◽  
Kiyoshi Sako ◽  
Hideki Takano ◽  
Takeshi Ishii ◽  
Mitsuru Sato
Keyword(s):  
Fission Product ◽  
Fast Reactor ◽  
Metallic Fuel ◽  
Gas Purge ◽  
Product Gas ◽  
Fuel Assemblies

scholarly journals Calculation of excore detector weighting functions for a sodium-cooled TRU burner mockup using MCNP5

2015 ◽  
Vol 5 (2) ◽  
pp. 15-25
Author(s):  
Viet Ha Pham Nhu ◽  
Min Jae Lee ◽  
Sunghwan Yun ◽  
Sang Ji Kim
Keyword(s):  
Fast Reactor ◽  
Power Distribution ◽  
Detector Response ◽  
Weighting Functions ◽  
Control Rod ◽  
The Core ◽  
Power Regulation ◽  
Fuel Assemblies ◽  
Control Rods ◽  
Horizontal Layers

Power regulation systems of fast reactors are based on the signals of excore detectors. The excore detector weighting functions, which establish correspondence between the core power distribution and detector signal, are very useful for detector response analyses, e.g., in rod drop experiments. This paper presents the calculation of the weighting functions for a TRU burner mockup of the Korean Prototype Generation-IV Sodium-cooled Fast Reactor (named BFS-76-1A) using the MCNP5 multi-group adjoint capability. For generation of the weighting functions, all fuel assemblies were considered and each of them was divided into ten horizontal layers. Then the weighting functions for individual fuel assembly horizontal layers, the assembly weighting functions, and the shape annealing functions at RCP (Reactor Critical Point) and at conditions under which a control rod group was fully inserted into the core while other control rods at RCP were determined and evaluated. The results indicate that the weighting functions can be considered relatively insensitive to the control rods position during the rod drop experiments and therefore those weighting values at RCP can be applied to the dynamic rod worth simulation for the BFS-76-1A.

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