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http://dx.doi.org/10.20466/KPVP.2016.12.1.070

Structural design and integrity evaluations for reactor vessel of PGSFR sodium-cooled fast reactor  

Koo, Gyeong Hoi (한국원자력연구원)
Kim, Sung Kyun (한국원자력연구원)
Publication Information
Transactions of the Korean Society of Pressure Vessels and Piping / v.12, no.1, 2016 , pp. 70-77 More about this Journal
Abstract
In this paper, the structural design and integrity evaluations for a reactor vessel of PGSFR sodium-cooled fast reactor(150MWe) are carried out in compliance with ASME BPV III, Division 5 Subsection HB. The reactor vessel is designed with a direct contact of primary sodium coolant to its inner surface and has a double vessel concept enclosing by containment vessel. To assure the structural integrity for 60 years design lifetime and elevated operating temperature of $545^{\circ}C$, which can invoke creep and creep-fatigue damage, the structural integrity evaluations are carried out in compliance with the ASME code rules. The design loads considered in this evaluations are primary loads and operation thermal cycling loads of normal heat-up and cool-down. From the evaluations, the PGSFR reactor vessel satisfies the ASME code limits but it was found that there is a little design margin of creep damage for inner surface at the region of cold pool free surface.
Keywords
Sodium-Cooled Fast Reactor; Reactor Vessel; Structural Integrity; Creep Damage; Creep-Fatigue;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
연도 인용수 순위
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2 ASME Boiler & Pressure Vessel Code Section III Division 5, "Rules for construction of nuclear facility components," 2013ed.
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