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Volume 109

Annals of Nuclear Energy

Volume 109

1

Uncertainty assessment for loss of flow accident of a 5 MW pool-type research reactor

Yum, Soo-been, Park, Su-ki

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.23 MB

english, 2017

2

Numerical studies of a helical coil once-through steam generator

Xia, Genglei, Yuan, Yuan, Peng, Minjun, Lv, Xing, Sun, Lin

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 827 KB

english, 2017

3

Investigation of density wave instability in once-through superheated steam generators using SIGHT

Tang, Yang, Zhou, Zhiwei, Zhang, Dabin

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 999 KB

english, 2017

4

Study on operator’s SA reliability in digital NPPs. Part 3: A quantitative assessment method

Li, Peng-cheng, Zhang, Li, Dai, Li-cao, Li, Xiao-Fang

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 382 KB

english, 2017

5

A review of research progress in heat exchanger tube rupture accident of heavy liquid metal cooled reactors

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.92 MB

english, 2017

6

Onset of Nucleate Boiling for subcooled flow through a one-side heated narrow rectangular channel

Al-Yahia, Omar S., Jo, Daeseong

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.59 MB

english, 2017

7

Numerical investigation of passive thermal-hydraulic performance of spent fuel dry-storage system for HTR-PM

Wang, Bing, Wang, Jinhua, Rizwan-uddin,

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 4.71 MB

english, 2017

8

Conceptual design of thorium based epithermal spectrum reactor

Choi, Hong Yeop, Park, Chang Je

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.58 MB

english, 2017

9

Experimental analysis of steam mixing and thermal stratification phenomena related to small steel containment studies

Wang, Shengfei, Wang, Yeyun, Zhuo, Weiqian, Niu, Fenglei, Yu, Yu, Guo, Zhangpeng, Shen, Yaou, Chen, Wei, Jiang, Xiaowei

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.28 MB

english, 2017

10

Characteristics and mechanism of bubble breakup in a bubble generator developed for a small TMSR

Sun, Licheng, Mo, Zhengyu, Zhao, Liang, Liu, Hongtao, Guo, Xie, Ju, Xiaofeng, Bao, Jingjing

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.24 MB

english, 2017

11

Finite volume lattice Boltzmann scheme for neutron/radiative transfer on unstructured mesh

Wang, Yahui, Yan, Liming, Ma, Yu, Li, Wei

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.26 MB

english, 2017

12

ATWS boron analysis for a BWR using the FNPK equation

Polo-Labarrios, M.A., Espinosa-Paredes, G., Lopéz, R., Nuñez-Carrera, A., Huerta, A., Vázquez-Rodríguez, R.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 766 KB

english, 2017

13

Influence of reflector materials and core coolant on the characteristics of accelerator driven systems

Panza, F., Osipenko, M., Ricco, G., Ripani, M., Saracco, P.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.89 MB

english, 2017

14

RELAP5 uncertainty evaluation using ROSA/LSTF test data on PWR 17% cold leg intermediate-break LOCA with single-failure ECCS

Takeda, Takeshi, Ohtsu, Iwao

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.50 MB

english, 2017

15

Neutronic calculations of the IAEA 10 MW MTR benchmark reactor via finite element method using COMSOL multiphysics code

Xoubi, Ned, Soliman, Abdelfattah Y.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.25 MB

english, 2017

16

Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor

Wang, Chenglong, Liu, Limin, Liu, Minghao, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.85 MB

english, 2017

17

Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1

Lim, Kukhee, Cho, Yongjin, Whang, Seokwon, Park, Hyun Sun

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 5.21 MB

english, 2017

18

Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5

Feng, Tangtao, Zhang, Dalin, Song, Ping, Tian, Wenxi, Li, Wei, Su, G.H., Qiu, Suizheng

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.95 MB

english, 2017

19

Experimental investigation on transient heat transfer in 2 × 2 bundle during depressurization from supercritical pressure

Li, Hongbo, Hu, Zhenxiao, Zhao, Meng, Gu, Hanyang, Lu, Donghua

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.59 MB

english, 2017

20

Experimental and numerical study on the circumferential pressure distribution on the wall of a 90° elbow pipe with circular section

Wang, Shiming, Ren, Cheng, Gui, Nan, Sun, Yanfei, Tu, Jiyuan, Yang, Xingtuan, Jiang, Shengyao

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.96 MB

english, 2017

21

Detection model of accidental control rod drop in PWR reactors with in-core and ex-core nuclear instrumentation using Delaunay triangulation

Souza, T.J., Medeiros, J.A.C.C., Gonçalves, A.C.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 4.97 MB

english, 2017

22

Validation of CFD analysis for rod bundle flow test with vaned spacer grids

Chen, Xi, Du, Sijia, Zhang, Yu, Yu, Hongxing, Li, Songwei, Peng, Huanhuan, Wang, Wei, Zeng, Wei

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.20 MB

english, 2017

23

A CFD-based simulation of fluid flow and heat transfer in the Intermediate Heat Exchanger of sodium-cooled fast reactor

Zhang, Xiaolong, Tseng, Peichi, Saeed, Muhammad, Yu, Jiyang

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.27 MB

english, 2017

24

Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY

Hu, Tianliang, Cao, Liangzhi, Wu, Hongchun, Du, Xianan, He, Mingtao

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 4.44 MB

english, 2017

25

Study on operator's SA reliability in digital NPPs. Part 2: Data-driven causality model of SA

Li, Peng-cheng, Zhang, Li, Dai, Li-cao, Li, Xiao-fang

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 314 KB

english, 2017

26

Rod ejection accident analysis for AP1000 with MOX/UOX mixed core loading

Selim, Hala K., Amin, Esmat H., Roushdy, Hassan E.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.73 MB

english, 2017

27

Preliminary study of applying adjoint-based mesh optimization method to nuclear power plant safety analysis

Son, Seongmin, Lee, Jeong Ik

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 4.68 MB

english, 2017

28

Diffusion theory model of the neutron number probability distribution in a subcritical multiplying assembly

Saxby, J.E.M., Prinja, Anil K., Eaton, M.D.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 4.10 MB

english, 2017

29

A study of photon interaction parameters in barium compounds

Manjunatha, H.C., Seenappa, L., Chandrika, B.M., Hanumantharayappa, Chikka

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 834 KB

english, 2017

30

Onset of Nucleate Boiling in narrow, rectangular channel for downward flow under low pressure

Song, Jung Hyun, Lee, Juhyung, Chang, Soon Heung, Jeong, Yong Hoon

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.17 MB

english, 2017

31

Analytical solution of the Telegraph Point Reactor Kinetics model during the cold start-up of a nuclear reactor

Altahhan, Muhammad Ramzy, Aboanber, Ahmed E., Abou-Gabal, Hanaa H.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 899 KB

english, 2017

32

Fluoride salt coolant properties for nuclear reactor applications: A review

Romatoski, R.R., Hu, L.W.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.68 MB

english, 2017

33

An automatic marine-organism monitoring system for the intake water of the nuclear power plant

Tang, Zhihong, Cheng, Feng, Jin, Xiaoxiang, Sun, Li, Bao, RuoYu, Liu, Yang

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 625 KB

english, 2017

34

A computational study of re-cycling the MTR research reactors with MOX fuel mixed with 241 Am, 242 Am and 243 Am as burnable absorbers actinides using the MCNP4C code

Shaaban, Ismail, Albarhoum, Mohamad

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.91 MB

english, 2017

35

Real-time simulations to enhance distributed on-line monitoring and fault detection in Pressurized Water Reactors

Peng, Min-jun, Wang, Hang, Yang, Xu, Liu, Yong-kuo, Guo, Liang-zhuang, Li, Wei, Jiang, Nan

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 5.25 MB

english, 2017

36

Supercritical transient analysis in coupled fuel debris systems of symmetric and asymmetric geometry using integral kinetic model

Tuya, Delgersaikhan, Obara, Toru

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 583 KB

english, 2017

37

Evaluation of spent fuel pool temperature and water level during SBO

Mochizuki, Hiroyasu

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.72 MB

english, 2017

38

Neutronic modeling and calculations of the ETRR-2 MTR reactor using COMSOL multiphysics code

Xoubi, Ned, Soliman, Abdelfattah Y.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.74 MB

english, 2017

39

A new cross section adjustment method of removing systematic errors in fast reactors

Takeda, Toshikazu, Yokoyama, Kenji, Sugino, Kazuteru

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.14 MB

english, 2017

40

Investigation of radiation shielding of the Containment Filtered Venting System for the various operating condition

Kim, Minhwa, Bang, Youngsuk, Lee, Doo Yong

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.13 MB

english, 2017

41

Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plant

Chen, Yen-Shu, Yuann, Yng-Ruey

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.22 MB

english, 2017

42

Capability of RELAP5 code to simulate the thermal-hydraulic characteristics of open natural circulation

Hou, Xiaofan, Sun, Zhongning, Lei, Wenjing

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 7.19 MB

english, 2017

43

Development and analysis of a regime map for predicting debris bed formation behavior

Cheng, Songbai, Wang, Shixian, Jiang, Guangyu, Yu, Jiahuan, Qian, Yujia, Gong, Pengfeng, Cui, Jinjiang

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.19 MB

english, 2017

44

Geometry pretreatment method for the 3D modular characteristic method based on AutoCAD

Liu, Zhouyu, Wu, Hongchun, Cao, Liangzhi

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.27 MB

english, 2017

45

Track truncation method for improving the computational efficiency of 2D matrix MOC

Zheng, Yong, Peng, Minjun

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.25 MB

english, 2017

46

Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF

Guo, Juanjuan, Liu, Shichang, Shang, Xiaotong, Huang, Shanfang, Wang, Kan

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.62 MB

english, 2017

47

Calculation of resonance self-shielding factors in a round disk using the enlarged Doppler Broadening Function

Palma, Daniel A.P., Almeida, Guilherme G., Gonçalves, Alessandro C.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 401 KB

english, 2017

48

Proposal to reload using MOX weapons grade in a BWR reactor

Hernandez, Hector, Castillo, Rogelio

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.92 MB

english, 2017

49

Analysis of single phase flow instability in U-tubes of steam generator

Yang, Bo, Wang, Chuan, Li, Xiao-Jun

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 945 KB

english, 2017

50

Dynamic modeling of AP1000 steam generator for control system design and simulation

Wan, Jiashuang, Wu, Shifa, Nuerlan, Areai, Zhao, Fuyu

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.52 MB

english, 2017

51

Thermal hydraulics analysis of a helical coil steam generator of a small modular reactor

Zaman, Fakhar Uz, Qureshi, Kamran, Haq, Inamul, Siddique, Waseem

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.94 MB

english, 2017

52

Performance verification of Passive Accident Mitigation Scheme (PAMS) under feedwater line break (FLB) accident

Shi, Er-bing, Wang, Chang, Hao, Rui, Fang, Chengyue, Xia, Genglei

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.22 MB

english, 2017

53

Modeling and experimental studies on air buoyant jets for application to small containments

Ma, Tengfei, Niu, Fenglei, Zhuo, Weiqian, Wang, Yeyun, Warraich, Taskeen, Azam, Safeer

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.96 MB

english, 2017

54

Use cases of Tucker decomposition method for reconstruction of neutron macroscopic cross-sections

Luu, Thi Hieu, Guillo, Matthieu, Maday, Yvon, Guérin, Pierre

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.06 MB

english, 2017

55

Design review and controllability assessment of the SMART-ITL secondary system for the SMART design with experimental investigation

Yun, Eunkoo, Bae, Hwang, Ryu, Sung-Uk, Yi, Sung-Jae, Park, Hyun-Sik

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.80 MB

english, 2017

56

Energy Production Demonstrator and Material Testing Station optimization for Megawatt proton beams

Pronskikh, Vitaly S., Mokhov, Nikolai V., Novitski, Igor, Tyutyunnikov, Sergey I.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.25 MB

english, 2017

57

Multiphysics modeling of novel UO 2 -BeO sandwich fuel performance in a light water reactor

Liu, Rong, Zhou, Wenzhong

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 4.49 MB

english, 2017

58

Evaluation of dose rate variation during very long term storage of RBMK-1500 reactor used fuel

Šmaižys, A., Poškas, P., Narkūnas, E.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.70 MB

english, 2017

59

Fission yield covariance matrices for the main neutron-induced fissioning systems contained in the JEFF-3.1.1 library

Terranova, N., Serot, O., Archier, P., De Saint Jean, C., Sumini, M.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.58 MB

english, 2017

60

A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding

Cinbiz, M. Nedim, Brown, Nicholas R., Terrani, Kurt A., Lowden, Rick R., Erdman, Donald

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.34 MB

english, 2017

61

Verification of kinetic capabilities of the GNOMER neutron diffusion code

Merljak, Vid, Kromar, Marjan, Trkov, Andrej

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.42 MB

english, 2017

62

Benchmark and demonstration of the CHD code for transient analysis of fast reactor systems

Hellesen, C., Qvist, S.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 766 KB

english, 2017

63

Assessment of spent nuclear fuel amounts to be managed based on disposal option in Republic of Korea

Park, Byung Heung

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 910 KB

english, 2017

64

Effect of power uprate on core damage frequency in a MBLOCA with multiple operator actions

Chen, Y.M., Lee, M., Chen, S.K.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 1.70 MB

english, 2017

65

Design analysis of DC electromagnetic pump for liquid sodium–CO 2 reaction experimental characterization

Lee, Geun Hyeong, Kim, Hee Reyoung

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.06 MB

english, 2017

66

Sensitivity analysis for the weighting factor in the least-square method for the PWR on-line power-distribution monitoring

Li, Zhuo, Cao, Liangzhi, Wu, Hongchun, Shen, Wei

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 2.30 MB

english, 2017

67

Accurate reflective boundary condition in the PN method

Yousefi, Mostafa, Zolfaghari, A., Minuchehr, A., Abbassi, M.R.

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 8.17 MB

english, 2017

68

Hydrogen distribution and Passive Autocatalytic Recombiner (PAR) mitigation in a PWR-KWU containment type

Lopez-Alonso, Emma, Papini, Davide, Jimenez, Gonzalo

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 3.83 MB

english, 2017

69

Editorial board

Journal:

Annals of Nuclear Energy

Année:

2017

Langue:

english

Fichier:

PDF, 49 KB

english, 2017