Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior
- 출판일
- 20240625
- ISSN
- (P)1738-5733 / (E)2234-358X
- 수록정보
- 권 6호 2332 ~ 2342쪽
논문 저자
| No |
이름 |
이메일 |
기관 |
| 1 |
Chenglong Wang |
- |
Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University |
| 2 |
Chen Wang |
- |
Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University |
| 3 |
Wenxi Tian |
- |
Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University |
| 4 |
Guanghui Su |
- |
Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University |
| 5 |
Suizheng Qiu |
- |
Department of Nuclear Science and Technology, State Key Lab. of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi'an Jiaotong University |