Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1

Author(s):  
Choon Sung Yoo ◽  
Byoung Chul Kim
2020 ◽  
Vol 6 (3) ◽  
Author(s):  
Petra Pónya ◽  
Gyula Csom ◽  
Sándor Fehér

Abstract Fast neutron irradiation causes embrittlement of the reactor pressure vessel (RPV) material; therefore, it may end operation life before design lifetime. Well-known method to recuperate crystal lattice dislocations is annealing. In the current version of thorium fueled supercritical water-cooled reactor (SCWR) design proposed by the Institute of Nuclear Technology at Budapest University of Technology and Economics (BME NTI), the supercritical fluid flows upward between the core barrel and the inner surface of the RPV thereby, the coolant would keep the RPV's temperature at ∼500 °C. This reverse coolant flow direction would decrease the embrittlement of RPV by constant annealing. To minimize the fast neutron flux increase, a relatively thin shielding connected to the inner surface of the barrel could be used. This presents fast neutron irradiation analysis, performed for different settings of the shielding to reduce fast neutron flux reaching the inner surface of RPV.


Author(s):  
Michal Košt´ál ◽  
Vít Klupák ◽  
Vojtěch Rypar ◽  
Evžen Losa ◽  
František Cvachovec ◽  
...  

2013 ◽  
Vol 434 (1-3) ◽  
pp. 347-356 ◽  
Author(s):  
B.Z. Margolin ◽  
E.V. Yurchenko ◽  
A.M. Morozov ◽  
N.E. Pirogova ◽  
M. Brumovsky

2000 ◽  
Vol 650 ◽  
Author(s):  
G. R. Odette ◽  
G. E. Lucas ◽  
D. Klingensmith

ABSTRACTSingle variable experiments on a set of reactor pressure vessel and model alloys with a range of controlled compositions show a systematic effect of neutron flux (ϕ) on hardening in the intermediate fluence (ϕt) regime. The data suggest that high ϕ and enhanced recombination by vacancy trapping by solutes delays the onset of radiation-enhanced precipitation hardening.


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