Retraction
Core design and analysis of a lead-bismuth cooled small modular reactor
Paper Information
Record ID:
40176
Author(s):
Journal:
Publication Date:
June 26, 2019
Retraction Date:
August 28, 2022
(3.2 years years ago)
Subjects:
Country:
🇨🇳 ChinaArticle Type:
Publisher:
Elsevier
Open Access:
Yes
PubMed ID:
Not indexed in PubMed
Retraction PubMed ID:
Not indexed in PubMed
Retraction Details
Retraction Reasons:
Nature of Retraction:
Retraction
Retraction Notice:
10.1016/j.anucene.2022.109416Citations (11)
11
Total Citations5
Post-Retraction(45.5%)
6
Pre-Retraction0
Same DayPost-Retraction Citation Analysis
0
Within 30 days
4
Within 1 year
0
After 2+ years
386
Days since retraction (latest)
Fuel cycle cost comparison between lead and sodium cooled fast reactors
Khaldoon Al-Dawood, Scott Palmtag
Nuclear Engineering and Design
Published: Sep 2023
2 citations
2 citations
386 days after retraction
Temperature Dependence of the Tensile Strength of Select Coolant Materials for Generation-IV Nuclear Reactors: Sodium, Lead and Bismuth
Ramesh Arumugam, R. Balasubramanian
JOM
Published: Mar 2023
2 citations
2 citations
211 days after retraction
A Design and Optimization Methodology for Liquid Metal Fast Reactors
Khaldoon Al-Dawood, Scott Palmtag
International Journal of Energy Research
Open Access
Published: Mar 2023
4 citations
4 citations
192 days after retraction
Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors
Qifan Yu, Yuliang Fang, Yafeng Zhao et al. (8 authors)
International Journal of Heat and Mass Transfer
Published: Feb 2023
24 citations
24 citations
178 days after retraction
Ideal tensile strength of select coolant materials for generation-IV nuclear reactors
Ramesh Arumugam, Balasubramanian Ramasamy
AIP conference proceedings
Published: Jan 2023
126 days after retraction
Single-phase flow in helical cruciform fuel assembly with conjugate heat transfer
Tenglong Cong, Rui Zhang, Bicheng Wang et al. (5 authors)
Progress in Nuclear Energy
Published: Mar 2022
42 citations
42 citations
160 days before retraction
Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer
Jie Liu, Ping Song, Dalin Zhang et al. (11 authors)
Nuclear Engineering and Technology
Open Access
Published: Feb 2022
14 citations
14 citations
208 days before retraction
Flow and heat transfer characteristics of liquid metal and supercritical CO2 in a twisted tube heat exchanger
Jiayuan Zhao, Liangxing Li, Wei Xie et al. (4 authors)
International Journal of Thermal Sciences
Published: Jan 2022
22 citations
22 citations
237 days before retraction
An IFDF accelerated parallel nodal SN method for XYZ geometry in SARAX code system
Zhitao Xu, Youqi Zheng, Hongchun Wu
Annals of Nuclear Energy
Published: Sep 2021
5 citations
5 citations
338 days before retraction
Thermal-hydraulics Design and Safety Analysis of Small Modular Lead-Bismuth Cooled Fast Reactors
Dalin Liu, Tan Jiaqi, Xiaojing Liu et al. (7 authors)
2021 11th International Conference on Power and Energy Systems (ICPES)
Published: Dec 2020
611 days before retraction
Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers
Di Wu, Chenglong Wang, Minyang Gui et al. (9 authors)
International Journal of Energy Research
Open Access
Published: Oct 2020
13 citations
13 citations
682 days before retraction
Quick Stats
Total Citations:
11
Years Since Retraction:
3.2 years
Open Access:
Yes
Last Checked:
Jul 24, 2025