scholarly journals Small power lead fast reactor with metallic fuel

2018 ◽  
Vol 2018 (1) ◽  
pp. 33-40 ◽  
Author(s):  
Georgij Levanovich Khorasanov ◽  
Dmitry Sergeevich Samokhin ◽  
Aleksandr Sergeevich Zevyakin ◽  
Evgenij Alekseevich Zemskov ◽  
Anatolij Ivanovich Blokhin

Over the past 30 years, the partners now collaborating in Europe on fast-reactor development have taken the technology from a theoretical possibility to an engineering reality. In that time there has been a progression from experimental zero energy facilities followed by small power-producing engineering test reactors, to prototype reactors and a large commercial-size reactor. The paper describes the highlights of the reactor programmes in the partner countries and by example illustrates the experience gained from reactor operation and some of the principal activities in the supporting development programme. These include such topics as fuel performance, fast-neutron physics, liquid-metal thermal hydraulics, sodium chemistry, instrumentation and safety aspects. The paper concludes by summarizing some of the main objectives of the current development programme, which is directed to the support of the European Fast Reactor design being prepared by the European design and construction companies.


2017 ◽  
Vol 486 ◽  
pp. 53-59 ◽  
Author(s):  
Seoung Woo Kuk ◽  
Ki Hwan Kim ◽  
Jong Hwan Kim ◽  
Hoon Song ◽  
Seok Jin Oh ◽  
...  

2016 ◽  
Vol 48 (2) ◽  
pp. 330-338 ◽  
Author(s):  
Donny Hartanto ◽  
Woong Heo ◽  
Chihyung Kim ◽  
Yonghee Kim

2016 ◽  
Vol 2016 ◽  
pp. 1-7
Author(s):  
Ki-Hwan Kim ◽  
Jong-Hwan Kim ◽  
Seok-Jin Oh ◽  
Jung-Won Lee ◽  
Ho-Jin Lee ◽  
...  

The fabrication technology for metallic fuel has been developed to produce the driver fuel in a PGSFR in Korea since 2007. In order to evaluate the irradiation integrity and validate the in-reactor of the starting metallic fuel with FMS cladding for the loading of the metallic fuel, U-10 wt.%Zr fuel rodlets were fabricated and evaluated for a verification of the starting driver fuel through an irradiation test in the BOR-60 fast reactor. The injection casting method was applied to U-10 wt.%Zr fuel slugs with a diameter of 5.5 mm. Consequently, fuel slugs per melting batch without casting defects were fabricated through the development of advanced casting technology and evaluation tests. The optimal GTAW welding conditions were also established through a number of experiments. In addition, a qualification test was carried out to prove the weld quality of the end plug welding of the metallic fuel rodlets. The wire wrapping of metallic fuel rodlets was successfully accomplished for the irradiation test. Thus, PGSFR fuel rodlets have been soundly fabricated for the irradiation test in a BOR-60 fast reactor.


1991 ◽  
Vol 93 (3) ◽  
pp. 305-329 ◽  
Author(s):  
Toru Hiraoka ◽  
Kiyoshi Sako ◽  
Hideki Takano ◽  
Takeshi Ishii ◽  
Mitsuru Sato

2015 ◽  
Vol 2015 ◽  
pp. 1-8 ◽  
Author(s):  
Jong-Hwan Kim ◽  
Ki-Hwan Kim ◽  
Chan-Bock Lee

Metallic fuel slugs of U–10Zr–5Mn (wt%), a surrogate alloy for the U–TRU–Zr (TRU: a transuranic element) alloys proposed for sodium-cooled fast reactors, were prepared by injection casting in a laboratory-scale furnace, and their characteristics were evaluated. As-cast U–Zr–Mn fuel rods were generally sound, without cracks or thin sections. Approximately 68% of the original Mn content was lost under dynamic vacuum and the resulting slug was denser than those prepared under Ar pressure. The concentration of volatile Mn was as per the target composition along the entire length of the rods prepared under 400 and 600 Torr. Impurities, namely, oxygen, carbon, silicon, and nitrogen, totaled less than 2,000 ppm, satisfying fuel criteria.


2014 ◽  
Vol 86 ◽  
pp. 71-79 ◽  
Author(s):  
S. Latha ◽  
M. Nandagopal ◽  
S. Panneer Selvi ◽  
K. Laha ◽  
M.D. Mathew

2017 ◽  
Vol 94 ◽  
pp. 194-201 ◽  
Author(s):  
L. Capriotti ◽  
S. Brémier ◽  
K. Inagaki ◽  
P. Pöml ◽  
D. Papaioannou ◽  
...  

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