Volume 130

Annals of Nuclear Energy

Volume 130

1

Fuel management code system against experimental measurements of the CMRR reactor

Wang, Guanbo, Qian, Dazhi, Ma, Jimin, Li, Rundong, Yuan, Shu, Leng, Jun, Dou, Haifeng, Tang, Bin

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 771 KB

2019

2

Development and validation of boron diffusion model in nuclear reactor core subchannel analysis

Yu, Hao, Wang, Mingjun, Cai, Rong, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.33 MB

2019

3

The computer aided cutting planning of components using genetic algorithms for decommissioning of a nuclear reactor

Tsai, Po-Chou, Huang, Xiaoxu, Hung, Yu-Hsiang, Huang, Chung-Hao, Smith, Shana

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.48 MB

2019

4

Neutronic modeling of debris beds for a criticality evaluation

Freiría López, M., Buck, M., Starflinger, J.

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.02 MB

2019

5

Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code

Mazaher, Meysam Ghaderi, Salehi, Ali Akbar, Vosoughi, Naser

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.05 MB

2019

6

Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line

Wang, Mingjun, Feng, Tangtao, Fang, Di, Hou, Ting, Tian, Wenxi, Su, G.H., Qiu, Suizheng

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 4.58 MB

english, 2019

7

The Laplace transform method for solving the burnup equation with external feed

Xia, Shaopeng, Chen, Jingen, Han, Jianlong, Guo, Wei, Cai, Xiangzhou

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 684 KB

english, 2019

8

Axial helium compressor for high-temperature gas-cooled reactor: A review

Tian, Zhitao, Jiang, Bin, Malik, Adil, Zheng, Qun

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 5.08 MB

english, 2019

9

Deflection predictions of involute-shaped fuel plates using a fully-coupled numerical approach

Curtis, Franklin G., Freels, James D., Ekici, Kivanc

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 1.96 MB

2019

10

Fuel management code system against experimental measurements of the CMRR reactor

Wang, Guanbo, Qian, Dazhi, Ma, Jimin, Li, Rundong, Yuan, Shu, Leng, Jun, Dou, Haifeng, Tang, Bin

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 771 KB

english, 2019

11

Development and validation of boron diffusion model in nuclear reactor core subchannel analysis

Yu, Hao, Wang, Mingjun, Cai, Rong, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.33 MB

english, 2019

12

Experimental investigation of the turbulent flow in a rod bundle channel with spacer grids

Qi, Peiyao, Li, Xing, Li, Xin, Qiao, Shouxu, Tan, Sichao, Du, Sijia, Chen, Yitung

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 8.78 MB

english, 2019

13

Sensitivity analysis of source intensity and time bin size for the Rossi-alpha method in a numerical reactor model

Kong, Chidong, Lee, Deokjung

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 684 KB

english, 2019

14

Neutronic modeling of debris beds for a criticality evaluation

Freiría López, M., Buck, M., Starflinger, J.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.02 MB

english, 2019

15

Implementation of a dynamic Monte Carlo method for transients analysis with thermal-hydraulic feedbacks using MCNPX code

Mazaher, Meysam Ghaderi, Salehi, Ali Akbar, Vosoughi, Naser

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.05 MB

english, 2019

16

Numerical investigation on the CHF model and prediction for the external cooling channel of lower head

Dan, Li, Changhong, Peng, Songwei, Li, Yun, Guo

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.26 MB

english, 2019

17

Experimental studies on bubble breakup mechanism in a venturi bubble generator

Song, Yuchen, Wang, Dezhong, Yin, Junlian, Li, Jingjing, Cai, Kangbei

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 4.94 MB

english, 2019

18

Characteristics of the high-temperature water film evaporation with countercurrent turbulent air flow in the duct

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.29 MB

english, 2019

19

Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials

Kim, Mi Jin, Kim, Wonkyeong, Lee, Deokjung, Lemaire, Matthieu, Lee, Hee-Jae, Sohn, Dong-Seong, Kwon, Hyukjoo

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.78 MB

english, 2019

20

Correlation diagnosis method for heterogeneous Monte Carlo eigenvalue simulations based on a diffusion approximation

Miao, Jilang, Forget, Benoit, Smith, Kord

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.14 MB

english, 2019

21

Off-design performance and power-control strategy for combined cycle coupled with high-temperature gas-cooled reactor

Qu, Xinhe, Yang, Xiaoyong, Wang, Jie

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.40 MB

english, 2019

22

Reactor physics analysis of a new Accident Tolerant Fuel called Fuel-in-Fibers

Hiscox, Briana, Shirvan, Koroush

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.74 MB

english, 2019

23

Investigation on transient thermal hydraulics of reduced scale passive residual heat removal heat exchanger in tank

Tao, Jiaqi, Gu, Hanyang, Xiong, Zhenqin, Jiang, Xing, Xie, Yongcheng

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.86 MB

2019

24

Evaluation of FRAPCON-4.0’s uncertainties predicting PCMI during power ramps

Feria, F., Herranz, L.E.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.60 MB

english, 2019

25

Investigation on transient thermal hydraulics of reduced scale passive residual heat removal heat exchanger in tank

Tao, Jiaqi, Gu, Hanyang, Xiong, Zhenqin, Jiang, Xing, Xie, Yongcheng

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.86 MB

english, 2019

26

A CFD/CSD coupled method with high order and its applications in flow induced vibrations of tube arrays in cross flow

Tang, Di, Bao, Shiyi, Luo, Lijia, Zhu, Hai, Cui, Hao

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 3.24 MB

english, 2019

27

The research on the heat transfer of a solid-core nuclear reactor cooled by heat pipe through a numerical simulation, considering the assembly gaps

Cao, Hanwen, Wang, Guanbo

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.79 MB

english, 2019

28

Preliminary interpretative analysis of the QUENCH-18 bundle test using SCDAPSim/mod3.5

Birchley, Jonathan C., Stuckert, J., Steinbrueck, M., Grosse, M.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 4.49 MB

english, 2019

29

Risk-informed approach for design optimization during low power and shutdown operation

Oh, Ji-Yong, Hwang, Seok-Won

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.02 MB

english, 2019

30

Comparison of sensitivity calculation between mathematical and physical adjoint in the 2-D/1-D transport solver KYADJ

Wu, Qu, Xu, Fei, Peng, Xingjie, Yu, Yingrui, Li, Qing, Wang, Kan

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.48 MB

english, 2019

31

A modal ACMFD formulation of the HEXNEM3 method for solving the time-dependent neutron diffusion equation

Kolev, Srebrin, Christoskov, Ivaylo

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 832 KB

english, 2019

32

Impact of shield elements on the WWER-440 reactor pressure vessel activation

Narkunas, Ernestas, Poskas, Gintautas, Smaizys, Arturas

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 4.60 MB

english, 2019

33

Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs

Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., Gorzel, A.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.45 MB

english, 2019

34

Error analysis of approximations and treatments commonly made in multi-group library and self-shielding calculation based on NECP-X

He, Qingming, Liu, Zhouyu, Cao, Liangzhi, Wu, Hongchun

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.65 MB

english, 2019

35

Risk-informed approach for design optimization during low power and shutdown operation

Oh, Ji-Yong, Hwang, Seok-Won

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 1.02 MB

2019

36

Comparison of sensitivity calculation between mathematical and physical adjoint in the 2-D/1-D transport solver KYADJ

Wu, Qu, Xu, Fei, Peng, Xingjie, Yu, Yingrui, Li, Qing, Wang, Kan

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 1.48 MB

2019

37

A modal ACMFD formulation of the HEXNEM3 method for solving the time-dependent neutron diffusion equation

Kolev, Srebrin, Christoskov, Ivaylo

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 832 KB

2019

38

Impact of shield elements on the WWER-440 reactor pressure vessel activation

Narkunas, Ernestas, Poskas, Gintautas, Smaizys, Arturas

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 4.60 MB

2019

39

Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs

Clifford, I., Pecchia, M., Mukin, R., Cozzo, C., Ferroukhi, H., Gorzel, A.

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.45 MB

2019

40

Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: Fission product release and transport analysis

Fernandez-Moguel, L., Rydl, A., Lind, T.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.39 MB

english, 2019

41

Methods of studying the effect of rough surfaces on reactivity in two-dimensional reactor physics problems

Williams, A.J.R., Williams, M.M.R., Eaton, M.D.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.37 MB

english, 2019

42

Corrigendum to ‘Uncertainty quantification of sodium-cooled fast reactor based on the UAM-SFR benchmarks: From pin-cell to full core’ [Ann. Nuclear Energy 128 (2019), 433–442]

Qiao, Liang, Zheng, Youqi, Wan, Chenghui

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 160 KB

english, 2019

43

Estimation of some neutron physics characteristics by Monte-Carlo method using the importance function

Gurevich, M.I., Kalugin, M.A., Oleynik, D.S., Shkarovsky, D.A.

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 997 KB

english, 2019

44

Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: Fission product release and transport analysis

Fernandez-Moguel, L., Rydl, A., Lind, T.

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.39 MB

2019