Volume 149

Annals of Nuclear Energy

Volume 149

1

Modeling and simulation of feedwater control system with multiple once-through steam generators in a sodium-cooled fast reactor (II): Control system simulation

Sun, Peiwei, Zhang, Xianshan

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.95 MB

2020

2

Decontamination of concrete waste from nuclear power plant decommissioning in South Korea

Han, Sangsoo, Hong, Seokju, Nam, Seongsik, Kim, Won-Seok, Um, Wooyong

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.61 MB

2020

3

Heat pipe failure accident analysis in megawatt heat pipe cooled reactor

Ma, Yugao, Chen, Erhui, Yu, Hongxing, Zhong, Ruicheng, Deng, Jian, Chai, Xiaoming, Huang, Shanfang, Ding, Shuhua, Zhang, Zhuohua

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 7.40 MB

2020

4

Measurement of HÃ¸gdahl neutron flux parameters in the SM1 subcritical reactor of the University of Pavia

Di Luzio, M., DâAgostino, G., Oddone, M.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 568 KB

2020

5

A sequential conjugate gradient method to estimate heat flux for nonlinear inverse heat conduction problem

Xiong, Ping, Deng, Jian, Lu, Tao, Lu, Qi, Liu, Yu, Zhang, Yong

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.38 MB

2020

6

The opportunities and challenges of micro heat piped cooled reactor system with high efficiency energy conversion units

Wang, D.Q., Yan, B.H., Chen, J.Y.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 722 KB

2020

7

Neutronics design for molten salt accelerator-driven system as TRU burner

Sugawara, Takanori

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.91 MB

2020

8

Stability analysis of predictor-corrector schemes for coupling neutronics and depletion

Cosgrove, P., Shwageraus, E., Parks, G.T.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.35 MB

2020

9

Population-based variance reduction for dynamic Monte Carlo

Legrady, David, Halasz, Mate, Kophazi, Jozsef, Molnar, Balazs, Tolnai, Gabor

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.02 MB

2020

10

Similarity analysis of thermal-fluid flow for thermal testing using scaled-down model of spent fuel storage cask

Lee, Ju-Chan, Bang, Kyung-Sik, Yu, Seung-Hwan, Choi, Woo-Seok, Ko, Sungho

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.95 MB

2020

11

Linear stability analysis of RELAP5 two-fluid model in nuclear reactor safety results

Saraswat, S.P., Munshi, P., Allison, C.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 6.54 MB

2020

12

Linking classical PRA models to a dynamic PRA

Mandelli, D., Wang, C., Parisi, C., Maljovec, D., Alfonsi, A., Ma, Z., Smith, C.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.86 MB

2020

13

Stability analysis of nuclear-coupled thermal hydraulics for a natural circulation lead-cooled fast reactor

Lu, Qiyue, Rizwan-uddin,

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.87 MB

2020

14

SMART with Trans-Critical CO2 power conversion system for maritime propulsion in Northern Sea Route, part 1: System design

Oh, Bong Seong, Kim, Yonghee, Kim, Sung Joong, Lee, Jeong Ik

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.90 MB

2020

15

Sensitivity and uncertainty analysis for the UAM-SFR sub-exercises with linear regression from random sampling

Zwermann, Winfried, Berner, Nadine, Aures, Alexander, Velkov, Kiril

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.99 MB

2020

16

Investigation on long-term daily load follow operation capability of soluble boron-free SMR

Jo, Bum Hee, Hah, Chang Joo

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.24 MB

2020

17

Two-phase modeling of water-air flow of dispersed and segregated flows

Godino, Dario M., Corzo, Santiago F., Ramajo, Damian E.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.94 MB

2020

18

Analysis of EBR-II pump run-up test with a best estimate plus uncertainty approach

Jeong, H.-Y., Jun, H.-Y., Ha, K.-S., Choi, C.-W., Bae, S.-W., Kang, S.-J.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.60 MB

2020

19

Loose parts detection method combining blind deconvolution with support vector machine

Meng, Jianlin, Su, Youbiao, Xie, Shilin

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 4.22 MB

2020

20

Evaluation of multi-cycle physics and economics considering end cycle optimization for a PWR

Son, Seungbeom, Lee, Jongwoo, Kim, Hyeongseog, Kim, Yonghee

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.98 MB

2020

21

Sub-channel code development of lead-bismuth eutectic fast reactor available for multiple fuel assembly structures

Deng, Jian, Lu, Qi, Wu, Di, Wang, Chenglong, Guo, Chao, Mi, Zhengpeng, Huang, Daishun, Yan, Mingyu, Wang, Xiaoyu, Chen, Xi, Li, Peiying

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.06 MB

2020

22

Research on fast intelligence multi-objective optimization method of nuclear reactor radiation shielding

Song, Yingming, Zhang, Zehuan, Mao, Jie, Lu, Chuan, Tang, Songqian, Xiao, Feng, Lyu, Huanwen

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.49 MB

2020

23

A probabilistic model-based diagnostic framework for nuclear engineering systems

Nguyen, Tat Nghia, Downar, Thomas, Vilim, Richard

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.12 MB

2020

24

Analysis of the drop dynamics of control rod assembly in a LBE-cooled research reactor

Arthur, Emmanuel Maurice, Zhang, Chaodong, Debrah, Seth Kofi, Yamoah, Stephen, Wang, Lei

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 3.74 MB

2020

25

Development of a method for quantifying relative importance of NPP cyber attack probability variables based on factor analysis and AHP

Kim, Yong Sik, Choi, Moon Kyoung, Han, Sang Min, Lee, Chanyoung, Seong, Poong Hyun

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.41 MB

2020

26

Implementation of an adaptive energy grid routine in NDEX for the processing of thermal neutron scattering cross sections

Wormald, J.L., Thompson, J.T., Trumbull, T.H.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 362 KB

2020

27

A modified unscented transformation method for uncertainty propagation in neutron induced cross section measurement

Matharu, Jagjit Singh, Devi, Vidya

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.38 MB

2020

28

Fast solution of neutron diffusion problem with movement of control rods

Helin, Gong, Wei, Chen, Chunyu, Zhang, Gong, Chen

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 791 KB

2020

29

and the generalized transverse integration nodal method

Chao, Yung-An, Peng, Lianghui, Tang, Chuntao

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.15 MB

2020

30

Improvement of the uncertainty method with model treatment and optimized global sensitivity analysis and its application to pressurized water reactor

Xiong, Qingwen, Gou, Junli, Shan, Jianqiang, Hui, Yongbo

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 4.02 MB

2020

31

Prediction of critical heat flux using Gaussian process regression and ant colony optimization

Jiang, B.T., Zhou, J., Huang, X.B., Wang, P.F.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 352 KB

2020

32

Interpretation of the JANUS Phase 7 shielding experiment with TRIPOLI-4Â® and quantification of uncertainties due to nuclear data

Hajji, Amine, Coquelet-Pascal, Christine, Blaise, Patrick

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 937 KB

2020

33

A POD reduced-order model for resolving the neutron transport problems of nuclear reactor

Sun, Yue, Yang, Junhe, Wang, Yahui, Li, Zhuo, Ma, Yu

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1003 KB

2020

34

Experimentally investigating phase separation and pressure drop as bubbly flow in a vertical branching T-junction

Wang, J.R., Huang, P.C., Ferng, Y.M.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 79 KB

2020

35

The development of spallation target and fuel handling system for China initiative accelerator driven system

Li, Jin-Yang, Gu, Long, Xu, Hu-Shan, Zhang, You-Peng, Yao, Cun-Feng, Sheng, Xin, Yang, Sheng, Fan, Da-Jun, Wang, Da-Wei

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 243 KB

2020

36

A data-driven strategy for xenon dynamical forecasting using dynamic mode decomposition

Gong, Helin, Yu, Yingrui, Peng, Xingjie, Li, Qing

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.09 MB

2020

37

Editorial Board

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 388 KB

2020

38

Experimental study on local fuelâcoolant interaction in molten pool with different melts

Cheng, Songbai, Dong, Yuhang, Chen, Xiaolin, Ye, Yiji, Chen, Yunhao

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 777 KB

2020

39

Multi-group equivalence in subgroup method based on generalized equivalence theory

Asim Shahzad, Muhammad, Cao, Liangzhi, He, Qingming, Xia, Fan, Li, Yunzhao

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.09 MB

2020

40

On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding

Avelar, Alan Matias, MourÃ£o, Marcelo Breda, Maturana, Marcos, Giovedi, Claudia, Abe, Alfredo Yuuitiro, Pedrassani, Rafaela, Su, Jian

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.15 MB

2020

41

Flow-induced acoustic resonances in closed tandem side branches with large diameter

Xiao, Yao, Huang, Chao, Li, Junlong, Zhang, Hengwei, Gu, Hanyang

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 178 KB

2020

42

Application of deep neural network for generating resonance self-shielded cross-section

Qin, Shuai, Zhang, Qian, Zhang, Jinchao, Liang, Liang, Zhao, Qiang, Wu, Hongchun, Cao, Liangzhi

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 212 KB

2020

43

Effect of debris combination on flow resistance of fuel assemblies

Liang, Ruixian, Wang, Da, Liu, Jun, Wang, Shengfei, Hao, Zulong, Tan, Sichao, Niu, Fenglei

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.15 MB

2020

44

Long-term thermal aging performance of welding structures in primary coolant pipes for nuclear power plants

Fan, Minyu, Chen, Mingya, Yu, Min, Jia, Wenqing, Li, Yuanfei, Cao, Yu, Xue, Fei, Yu, Weiwei

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 318 KB

2020

45

Experimental investigations on penetration failure by tube ejection for an APR1400 ICI nozzle during a severe accident

An, Sang Mo, Jung, Jaehoon, Kim, Hwan Yeol

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.06 MB

2020

46

Geometric sensitivity analysis of generalized response function with RMC code

Shi, Guanlin, Feng, Zhiyuan, Jia, Conglong, Wang, Kan, Huang, Shanfang, Cheng, Quan

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 329 KB

2020

47

Integral effect test results on the effect of asymmetric supply of feedwater during a station blackout transient of pressurized water reactor

Kang, Kyoung-Ho, Bae, Byoung-Uhn, Kim, Jong-Rok, Park, Yu-Sun, Lee, Jae-Bong, Cho, Seok, Choi, Nam-Hyun, Choi, Ki-Yong

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 901 KB

2020

48

A comparison of three algorithms applied in thermal-hydraulics and neutronics codes coupling for lbe-cooled fast reactor

Yang, Dongmei, Liu, Xiaojing, Zhang, Tengfei, Cheng, Xu

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 1.51 MB

2020

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