Volume 113

Annals of Nuclear Energy

Volume 113

1

Reactor design strategy to support spectral variability within a sodium-cooled fast spectrum materials testing reactor

Scherr, Jonathan, Tsvetkov, Pavel

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.71 MB

english, 2018

2

Criticality and uncertainty assessment of assembly misloading in BWR transportation cask

Radaideh, Majdi I., Price, Dean, Kozlowski, Tomasz

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.76 MB

english, 2018

3

Fourier analysis of the RELAP5/3D adaptive time-stepping scheme on a natural circulation loop

Braz Filho, Francisco A., Ribeiro, Guilherme B., Caldeira, Alexandre D.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.55 MB

english, 2018

4

An improved simplified method of evaluating severe accident source term in the containment of AP1000

Sun, Xiaohui, Cao, Xinrong, Shi, Xingwei

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.78 MB

english, 2018

5

Artificial neural network approximations of linear fractional neutron models

Vyawahare, Vishwesh A., Espinosa-Paredes, Gilberto, Datkhile, Gaurav, Kadam, Pratik

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 4.01 MB

english, 2018

6

Investigation of thermal hydraulic behavior of SBLOCA tests in SMART-ITL facility

Kim, Yeon-Sik, Bae, Hwang, Jeon, Byong-Guk, Bang, Yoon-Gon, Yi, Sung-Jae, Park, Hyun-Sik

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.13 MB

english, 2018

7

Nonlinear dynamic model of Molten-Salt Reactor Experiment – Validation and operational analysis

Singh, Vikram, Wheeler, Alexander M., Lish, Matthew R., Chvála, Ondřej, Upadhyaya, Belle R.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.74 MB

english, 2018

8

Rod insertion method analysis – A methodology update and comparison to boron dilution method

Merljak, Vid, Kromar, Marjan, Trkov, Andrej

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 969 KB

english, 2018

9

Verification of SuperMC for MNSRs core analysis: The case of Ghana Research Reactor-I

Baidoo, I.K., Li, B., Yang, Q., Song, J., Hu, L.Q.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.67 MB

english, 2018

10

Investigation of the thermal characteristics of condensers in nuclear power plant by simulation with zoning model

Sun, Ji-Lin, Xue, Ruo-Jun, Peng, Min-Jun

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.28 MB

english, 2018

11

Investigation of droplet behaviors for spray cooling using level set method

Shahmohammadi Beni, Mehrdad, Zhao, Jiyun, Yu, K.N.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.07 MB

english, 2018

12

Accelerated polynomial axial expansions for full 3D neutron transport MOC in the APOLLO3® code system as applied to the ASTRID fast breeder reactor

Santandrea, Simone, Graziano, Laurent, Sciannandrone, Daniele

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 9.32 MB

english, 2018

13

Analysis on hydrogen control system in AP1000 NPP

Lyu, Xuefeng, Xun, Zeyun, Ji, Ke, Lee, Xiaobo, Wang, Shengfei, Yu, Yu, Chen, Long

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.25 MB

english, 2018

14

Stochastic uncertainty quantification for safety verification applications in nuclear power plants

Boafo, Emmanuel, Gabbar, Hossam A.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.84 MB

english, 2018

15

Accuracy and analysis of the iteratively coupling 2D/3D method for the three-dimensional transport calculations

Liu, Zhouy, Liang, Liang, Chen, Jun, Zhao, Chen, Wu, Hongchun

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.53 MB

english, 2018

16

Analysis of delayed neutrons’ contribution for the maximum to average flux ratio in an annular pulsed reactor by Finite Volume Method

da Silva, Mário Augusto Bezerra, Narain, Rajendra

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 457 KB

english, 2018

17

Machine learning based system performance prediction model for reactor control

Zeng, Yuyun, Liu, Jingquan, Sun, Kaichao, Hu, Lin-wen

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.30 MB

english, 2018

18

Development of a new empirical correlation for steam condensation rates in the presence of air outside vertical smooth tube

Fan, Guangming, Tong, Pan, Sun, Zhongning, Chen, Yitung

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.32 MB

english, 2018

19

Validation of SuperMC code by simulating a Metal-cooled fast reactor – BFS-62-3A

Jamil, Zeeshan, Yang, Qi, Song, Jing, Jia, Jing, Wu, Yican

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.95 MB

english, 2018

20

Fault detection, identification and reconstruction of sensors in nuclear power plant with optimized PCA method

Li, Wei, Peng, Minjun, Liu, Yongkuo, Jiang, Nan, Wang, Hang, Duan, Zhiyong

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 4.79 MB

english, 2018

21

Neutron noise simulation using ACNEM in the hexagonal geometry

Hosseini, Seyed Abolfazl, Vosoughi, Naser, Vosoughi, Javad

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 5.72 MB

english, 2018

22

CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor

Chen, Jing, Zhang, Dalin, Song, Ping, Wang, Xinan, Wang, Shibao, Liang, Yu, Qiu, Suizheng, Zhang, Yapei, Wang, Mingjun, Su, G.H.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 7.47 MB

english, 2018

23

Numerical simulation of external inertia and compressibility effects on the dynamic instabilities of two-phase boiling flows in horizontal parallel channels

Bakhshan, Y., Kazemi, S.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.27 MB

english, 2018

24

Effects of downward-facing surface type and inclination on critical heat flux during pool boiling

Gong, H., Wang, L., Khan, A.R., Erkan, N., Okamoto, K.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.94 MB

english, 2018

25

Evaluation of an accident management strategy using an emergency water injection in a reference PWR SFP

Ahn, Kwang-Il, Jung, YongHun, Shin, Jae-Uk, Kim, Won-Tae

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 7.22 MB

english, 2018

26

Assessment of primary and secondary bleed and feed procedures during a Station Blackout in a German Konvoi PWR using ASTECV2.0

Gómez-García-Toraño, Ignacio, Sánchez-Espinoza, Víctor-Hugo, Stieglitz, Robert, Queral, César, Rebollo, María-José

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 5.76 MB

english, 2018

27

Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure

Xiao, Yao, Hu, Zhenxiao, Chen, Shuo, Gu, Hanyang

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.47 MB

english, 2018

28

Neutronic properties of high-temperature gas-cooled reactors with thorium fuel

Shamanin, I.V., Grachev, V.M., Chertkov, Yu.B., Bedenko, S.V., Mendoza, O., Knyshev, V.V.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.76 MB

english, 2018

29

Measurements of the total neutron cross sections of 93 Nb by using the filtered neutron beams

Anh, Tran Tuan, Son, Pham Ngoc, Tan, Vuong Huu

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.00 MB

english, 2018

30

Development and validation of the BERKUT fuel rod module of the EUCLID/V1 integrated computer code

Veprev, D.P., Boldyrev, A.V., Chernov, S.Yu., Mosunova, N.A.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.02 MB

english, 2018

31

Concentration-dependent activity coefficients of lanthanides in liquid bismuth for the FHR primary coolant cleanup

Wang, Yafei, Zhou, Wentao, Guo, Shaoqiang, Zhang, Jinsuo

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.09 MB

english, 2018

32

Discontinuous Galerkin spatial discretisation of the neutron transport equation with pyramid finite elements and a discrete ordinate (S N ) angular approximation

O’Malley, B., Kópházi, J., Eaton, M.D., Badalassi, V., Warner, P., Copestake, A.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.47 MB

english, 2018

33

Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors

Naceur, A., Marleau, G.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.34 MB

english, 2018

34

CALLISTO-SPK: A Stochastic Point Kinetics code for performing low source nuclear power plant start-up and power ascension calculations

Cooling, C.M., Williams, M.M.R., Eaton, M.D.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 669 KB

english, 2018

35

Multigroup Monte Carlo on GPUs: Comparison of history- and event-based algorithms

Hamilton, Steven P., Slattery, Stuart R., Evans, Thomas M.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.07 MB

english, 2018

36

AETIUS solutions for Kobayashi 3D benchmarks with the first collision source method on the volume source and unstructured tetrahedral mesh

Kim, Jong Woon, Lee, Young-Ouk

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 16.78 MB

english, 2018

37

Multi-scale analysis of an ATLAS-MSLB test using the coupled CUPID/MARS code

Park, Ik Kyu, Cho, Seok, Kang, Doo Hyuk

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.57 MB

english, 2018

38

Beta-effective sensitivity and uncertainty analysis of MYRRHA reactor for possible use in nuclear data validation and improvement

Kodeli, Ivan A.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.33 MB

english, 2018

39

Thorium as an additive for improved neutronic properties in boiling water reactor fuel

Insulander Björk, Klara, Netterbrant, Christer

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.35 MB

english, 2018

40

The evolution of PBIL algorithm when used to solve the nuclear reload optimization problem

da Silva, Márcio Henrique, Legey, Ana Paula, Mól, Antônio Carlos de A.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 527 KB

english, 2018

41

Numerical comparison of bubbling in a waste glass melter

Guillen, Donna Post, Cambareri, Joseph, Abboud, Alexander W., Bolotnov, Igor A.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 4.11 MB

english, 2018

42

Validation of the MCU-PTR computational model of beryllium poisoning using selected experiments at the IRT-T research reactor

Shchurovskaya, M.V., Alferov, V.P., Geraskin, N.I., Radaev, A.I., Naymushin, A.G., Chertkov, Yu.B., Anikin, M.N., Lebedev, I.I.

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1.01 MB

english, 2018

43

Four-bar linkage modeling and kinematics analysis of an in-vessel transfer system for Prototype Gen-IV Sodium-cooled Fast Reactor

Lim, Dong-Won, Lee, Jae-Han, Kim, Sung-Kyun

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 3.21 MB

english, 2018

44

Numerical optimization of Rhodium Self-Powered Neutron Detector

Zhang, Qingmin, Liu, Xinxin, Deng, Bangjie, Cao, Liangzhi, Tang, Chuntao

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 1006 KB

english, 2018

45

Editorial Board

Journal:

Annals of Nuclear Energy

Year:

2018

File:

PDF, 27 KB

2018

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