Volume 90

Annals of Nuclear Energy

Volume 90

1

Natural convection cooling characteristics in a plate type fuel assembly of Kyoto University Research Reactor during loss of coolant accident

Ito, Daisuke, Saito, Yasushi

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.27 MB

english, 2016

2

Calculation and updating of Common Cause Failure unavailability by using alpha factor model

Zubair, Muhammad, Amjad, Qazi Muhammad Nouman

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.03 MB

english, 2016

3

A statistical analysis in the BWR fuel lattice design

Casillo-Méndez, José Alejandro, Chávez, Verónica Jáuregui, Ortiz-Servin, Juan José, Montes-Tadeo, José Luis, Perusquía, Raúl, Morales, Luis B.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1015 KB

english, 2016

4

Developing a safe and high performance fuel management optimization for MTRs using stochastic knowledge base searches

Hedayat, Afshin

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.61 MB

english, 2016

5

Neutron-induced reaction on 233U

Su, Xinwu, Han, Yinlu, Cai, Chonghai

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.26 MB

english, 2016

6

Neutron flux estimation using Particle-

Tamboli, Prakash Kumar, Duttagupta, Siddhartha P., Roy, Kallol

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 832 KB

english, 2016

7

Study on the relation between Doppler reactivity coefficient and resonance integrals of Thorium and Uranium in PWR fuels

Dobuchi, Noboru, Takeda, Satoshi, Kitada, Takanori

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 677 KB

english, 2016

8

Determination of the power density distribution in a PWR reactor based on neutron flux measurements at fixed reactor incore detectors

Dias, A.M., Silva, F.C.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.88 MB

english, 2016

9

MELCOR 2.1 analysis of melt behavior in a BWR lower head during LOCA and SBO accident

Li, Gen, Liu, Ming, Wang, Jinshi, Chong, Daotong, Yan, Junjie

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.19 MB

english, 2016

10

Effective temperatures and scattering cross sections in water mixtures determined by Deep Inelastic Neutron Scattering

Dawidowski, J., Rodríguez Palomino, L.A., Márquez Damián, J.I., Blostein, J.J., Cuello, G.J.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.41 MB

english, 2016

11

Temperature control characteristics analysis of lead-cooled fast reactor with natural circulation

Yang, Minghan, Song, Yong, Wang, Jianye, Xu, Peng, Zhang, Guangyu

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.61 MB

english, 2016

12

Soft computing technique for developing turbine cycle model of Chinshan Nuclear Power Plant Unit 2

Chan, Yea-Kuang, Tsai, Yu-Ching

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 6.12 MB

english, 2016

13

Assessment of fission product inventory considering axial burnup of a fuel assembly

Jeong, Hae Sun, Jeong, Hyo Joon, Kim, Eun Han, Han, Moon Hee, Hwang, Won Tae

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.04 MB

english, 2016

14

Application of melt and refining procedures in the CANDLE reactor concept

Karim, Julia Abdul, Nishiyama, Jun, Obara, Toru

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.06 MB

english, 2016

15

Reactor physics analysis of the SPERT III E-core with Tripoli-4®

Zoia, Andrea, Brun, Emeric

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 5.43 MB

english, 2016

16

Analysis of oxidation influence on steam explosion energetics

Leskovar, Matjaž, Centrih, Vasilij, Uršič, Mitja

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.52 MB

english, 2016

17

Non symmetric alternating direction explicit method applied to the calculation of ADS transients

Figueira, Adriano Jorge, Alvim, Antonio Carlos Marques, da Silva, Fernando Carvalho

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.04 MB

english, 2016

18

Fault diagnosis of Pakistan Research Reactor-2 with data-driven techniques

Jamil, Farhan, Abid, Muhammad, Haq, Inamul, Khan, Abdul Qayyum, Iqbal, Masood

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 670 KB

english, 2016

19

Application of the inverse generalized perturbation theory to the optimization of fuel assembly design

Dall’Osso, Aldo

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 392 KB

english, 2016

20

Improved methods of online monitoring and prediction in condensate and feed water system of nuclear power plant

Wang, Hang, Peng, Min-jun, Wu, Peng, Cheng, Shou-yu

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.85 MB

english, 2016

21

A comparative study of leakage and diffusion coefficient models for few-group cross section generation with the Monte Carlo method

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.58 MB

english, 2016

22

Thermal–hydraulic design and analysis code development for steam generator of CFR600

Sun, Peiwei, Wang, Zi, Zhang, Jianmin, Su, Guanghui

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 802 KB

english, 2016

23

Investigation on sloshing and vibration mitigation of water storage tank of AP1000

Zhao, Chunfeng, Chen, Jianyun, Xu, Qiang, Wang, Jingfeng, Wang, Bo

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 5.01 MB

english, 2016

24

Sensitivity and uncertainty analyses of reactivities for PWR cells with

Foad, Basma, Takeda, Toshikazu

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.39 MB

english, 2016

25

Experimental study on the effect of wall-subcooling on condensation heat transfer in the presence of noncondensable gases in a horizontal tube

Xu, Huiqiang, Sun, Zhongning, Gu, Haifeng, Li, Hao

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.67 MB

english, 2016

26

Unavailability estimation of shutdown system of a fast reactor by Monte Carlo simulation

Ramakrishnan, M.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.18 MB

english, 2016

27

Advanced operation strategy for feed-and-bleed operation in an OPR1000

Kim, Bo Gyung, Yoon, Ho Joon, Kim, Jaewhan, Kang, Hyun Gook

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.00 MB

english, 2016

28

Remark on the neutron noise induced by propagating perturbations in an MSR

Dykin, V., Pázsit, I., Sanchez, R.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.35 MB

english, 2016

29

Investigation on thermal stratification and turbulent penetration in a pressurizer surge line with an overall out-surge flow

Zhang, Y., Lu, T., Jiang, P.X., Zhu, Y.H., Wu, J., Liu, C.L.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 7.16 MB

english, 2016

30

Criticality calculations of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI

Bostelmann, Friederike, Hammer, Hans R., Ortensi, Javier, Strydom, Gerhard, Velkov, Kiril, Zwermann, Winfried

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.73 MB

english, 2016

31

Fuel-steel mixing and radial mesh effects in power excursion simulations

Chen, X.-N., Rineiski, A., Gabrielli, F., Andriolo, L., Vezzoni, B., Li, R., Maschek, W., Kiefhaber, E.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.01 MB

english, 2016

32

Nuclear data uncertainties propagation methods in Boltzmann/Bateman coupled problems: Application to reactivity in MTR

Frosio, Thomas, Bonaccorsi, Thomas, Blaise, Patrick

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.87 MB

english, 2016

33

Thermal-hydraulic modelling of the Cold Neutron Source thermosiphon system

Pavlou, Tom, Ho, Mark, Yeoh, Guan Heng, Lu, Weijian

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 5.79 MB

english, 2016

34

Efficient reduction and modularization for large fault trees stored by pages

Chen, Shanqi, Wang, Jin, Wang, Jiaqun, Wang, Fang, Hu, Liqin

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 450 KB

english, 2016

35

Analysis of LBLOCA using best estimate plus uncertainties for three-loop nuclear power plant power uprate

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.61 MB

english, 2016

36

Conjugate heat transfer investigation of core damage propagation during total instantaneous blockage in SFR fuel subassembly

Ravi, L., Velusamy, K., Chellapandi, P.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 5.62 MB

english, 2016

37

Editorial board

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 56 KB

english, 2016

38

NAFCON-SF: A sodium spray fire code for evaluating thermal consequences in SFR containment

S., Muthu Saravanan, P., Mangarjuna Rao, Nashine, B.K., P., Selvaraj, P., Chellapandi

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.50 MB

english, 2016

39

Linear heat generation rate for breaking plastic strain limit of cladding in a BWR fuel rod type

Hernandez-Lopez, Hector, Lucatero, Marco A.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.43 MB

english, 2016

40

A novel domain overlapping strategy for the multiscale coupling of CFD with 1D system codes with applications to transient flows

Grunloh, T.P., Manera, A.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.11 MB

english, 2016

41

Probabilistic approach for decay heat uncertainty estimation using URANIE platform and MENDEL depletion code

Tsilanizara, A., Gilardi, N., Huynh, T.D., Jouanne, C., Lahaye, S., Martinez, J.M., Diop, C.M.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 821 KB

english, 2016

42

Galerkin partial least-square SN (GpLS–SN) method for fixed source problems in the neutron transport theory

Araujo, Lenilson M., do Carmo, Eduardo G.D., da Silva, Fernando C.

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 7.15 MB

english, 2016

43

Real variance analysis of Monte Carlo eigenvalue calculation by McCARD for BEAVRS benchmark

Park, Ho Jin, Lee, Hyun Chul, Shim, Hyung Jin, Cho, Jin Young

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.10 MB

english, 2016

44

Determining the axial power profile of partly flooded fuel in a compact core assembled in reactor LR-0

Košťál, Michal, Švadlenková, Marie, Baroň, Petr, Rypar, Vojtěch, Milčák, Ján

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.16 MB

english, 2016

45

Preliminary analysis of radiation characteristic at upper section of Accelerator Driven Subcritical System

Li, Bin, Yang, Qi, Chang, Bo, Zheng, Huaqing, Jiang, Jieqiong, Liu, Chao

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.20 MB

english, 2016

46

Nonoverlapping local/global iterations with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis—II: Parallelization and Predictor–Corrector Quasi-Static method application

Cho, Bumhee, Cho, Nam Zin

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 4.95 MB

english, 2016

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