Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water
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作者:
Sukarman
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Waseda Univ, Grad Sch Adv Sci & Engn, Cooperat Major Nucl Energy, Shinjuku Ku, Nishi Waseda Campus,3-4-1,Okubo, Tokyo 1698555, JapanWaseda Univ, Grad Sch Adv Sci & Engn, Cooperat Major Nucl Energy, Shinjuku Ku, Nishi Waseda Campus,3-4-1,Okubo, Tokyo 1698555, Japan
Sukarman
[1
]
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Yamaji, Akifumi
[1
]
Someya, Takayuki
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Waseda Univ, Grad Sch Adv Sci & Engn, Cooperat Major Nucl Energy, Shinjuku Ku, Nishi Waseda Campus,3-4-1,Okubo, Tokyo 1698555, JapanWaseda Univ, Grad Sch Adv Sci & Engn, Cooperat Major Nucl Energy, Shinjuku Ku, Nishi Waseda Campus,3-4-1,Okubo, Tokyo 1698555, Japan
Someya, Takayuki
[1
]
机构:
[1] Waseda Univ, Grad Sch Adv Sci & Engn, Cooperat Major Nucl Energy, Shinjuku Ku, Nishi Waseda Campus,3-4-1,Okubo, Tokyo 1698555, Japan
supercritical light water reactor;
compound system doubling time (CSDT);
fast breeder reactor (FBR);
tightly packed fuel assembly (TPFA);
tight lattice fuel assembly (TLFA);
D O I:
10.1115/1.4037719
中图分类号:
TL [原子能技术];
O571 [原子核物理学];
学科分类号:
0827 ;
082701 ;
摘要:
The authors look for an attractive light water reactor (LWR) concept, which achieves high breeding performance with respect to the compound system doubling time (CSDT). In the preceding study, a high breeding fast reactor concept, cooled by supercritical pressure light water (Super FBR), was developed using tightly packed fuel assembly (TPFA) concept, in which fuel rods were arranged in a hexagonal lattice and packed by contacting each other. However, the designed concept had characteristics, which had to be improved, such as low power density (7.4 kW/m), large core pressure loss (1.02 MPa), low discharge burnup (core average: 8 GWd/t), and low coolant temperature rise in the core (38 degrees C). The aim of this study is to clarify the main issues associated with improvement of the Super FBR with respect to these design parameters and to show the improved design. The core design is carried out by fully coupled three-dimensional neutronics and single-channel thermal-hydraulic core calculations. The design criteria are negative void reactivity, maximum linear heat generation rate (MLHGR) of 39 kW/m, and maximum cladding surface temperature (MCST) of 650 degrees C for advanced stainless steel. The results show that significant improvement is possible with respect to the core thermal-hydraulic characteristics with minimal deterioration of CSDT by replacing TPFA with the commonly acknowledged hexagonal tight lattice fuel assembly (TLFA). Further design studies are necessary to improve the core enthalpy rise by reducing the radial power swing and power peaking.
机构:
Minist Environm Protect, Nucl & Radiat Safety Ctr, 2nd East Floor,Huike Bldg,Xi Si Huan North Rd, Beijing 100142, Peoples R ChinaMinist Environm Protect, Nucl & Radiat Safety Ctr, 2nd East Floor,Huike Bldg,Xi Si Huan North Rd, Beijing 100142, Peoples R China
Zhao Chuanqi
Wang Kunpeng
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机构:
Minist Environm Protect, Nucl & Radiat Safety Ctr, 2nd East Floor,Huike Bldg,Xi Si Huan North Rd, Beijing 100142, Peoples R ChinaMinist Environm Protect, Nucl & Radiat Safety Ctr, 2nd East Floor,Huike Bldg,Xi Si Huan North Rd, Beijing 100142, Peoples R China
Wang Kunpeng
Cao Liangzhi
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机构:
Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xianning Xi Rd 28, Xian 710049, Shaanxi, Peoples R ChinaMinist Environm Protect, Nucl & Radiat Safety Ctr, 2nd East Floor,Huike Bldg,Xi Si Huan North Rd, Beijing 100142, Peoples R China
Cao Liangzhi
Zheng Youqi
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机构:
Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xianning Xi Rd 28, Xian 710049, Shaanxi, Peoples R ChinaMinist Environm Protect, Nucl & Radiat Safety Ctr, 2nd East Floor,Huike Bldg,Xi Si Huan North Rd, Beijing 100142, Peoples R China
Zheng Youqi
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE,
2018,
4
(01):
机构:
Hungarian Acad Sci KFKI, Atom Energy Res Inst, H-1525 Budapest, HungaryKarlsruhe Inst Technol, Inst Nucl & Energy Technol IKET, D-76344 Eggenstein Leopoldshafen, Germany