Volume 88

Progress in Nuclear Energy

Volume 88

1

Corrosion mitigation in coolant systems in nuclear power plants

Chajduk, Ewelina, Bojanowska-Czajka, Anna

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 558 KB

english, 2016

2

Neutronic evaluation of coating and cladding materials for accident tolerant fuels

Younker, Ian, Fratoni, Massimiliano

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.36 MB

english, 2016

3

Space independent xenon oscillations control in VVER reactor: A bifurcation analysis approach

Zarei, M., Ghaderi, R., Minuchehr, A.

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.91 MB

english, 2016

4

On an improved box-scheme finite difference method based on the relative event probabilities

Vagheian, Mehran, Ochbelagh, Dariush Rezaei, Gharib, Morteza

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.96 MB

english, 2016

5

Reactivity temperature coefficients for the HEU and LEU fuel of the MNSR reactor

Dawahra, S., Khattab, K., Saba, G.

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 986 KB

english, 2016

6

Application of vadose zone approach for prediction of radionuclide transfer from near-surface disposal facility

Jakimavičiūtė-Maselienė, Vaidotė, Mažeika, Jonas, Motiejūnas, Stasys

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 516 KB

english, 2016

7

Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system

Margulis, Marat, Gilad, Erez

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 6.53 MB

english, 2016

8

Are shocks to nuclear energy consumption per capita permanent or temporary? A global perspective

Zhu, Huiming, Guo, Peng

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.68 MB

english, 2016

9

Benchmarking verification of the control rod effects on the MTR core parameters using the MTR-PC and MCNP codes throughout 3D core modeling and rod-drop experiment

Hedayat, Afshin

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 815 KB

english, 2016

10

Implementation of cyber security for safety systems of nuclear facilities

Park, JaeKwan, Suh, YongSuk, Park, Cheol

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 548 KB

english, 2016

11

Pressure distribution in the containment of VVER-1000 during the first seconds of large break LOCA

Rahgoshay, M., Hashemi-Tilehnoee, M.

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.03 MB

english, 2016

12

Microstructural evolution of as-cast Th–U alloys

Das, Santanu, Roy, S.B., Chaudhari, G.P., Daniel, B.S.S.

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 5.52 MB

english, 2016

13

Lumped pseudo fission products during burnup step in MCNP5-ORIGEN coupling system

Benkharfia, Hocine, Zidi, Tahar, Belgaid, Mohamed

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.55 MB

english, 2016

14

Safety analysis of LBLOCA in BDBA scenarios for the Bushehr's VVER-1000 nuclear power plant

Pirouzmand, Ahmad, Ghasemi, Armin, Faghihi, Farshad

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.11 MB

english, 2016

15

Dancoff factor analysis for pebble bed fluoride salt cooled high temperature reactor

Qin, Wei, Yang, Kun, Chen, Jingen, Cai, Xiangzhou

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.44 MB

english, 2016

16

Control rod drop hydrodynamic analysis for a pressurized water reactor

Rabiee, Ataollah, Atf, Alireza

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.66 MB

english, 2016

17

A sensitivity analysis of thermal lattices kinetic parameters with respect to the spectral weighting function using ultrafine BN method

Fallah, Vahid Farhang, Salehi, Ali Akbar, Vosoughi, Naser, Ayyoubzadeh, Seyed Mohsen

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.67 MB

english, 2016

18

Calculation of radial burnup and nuclides atom density distributions in a VVER-1000 fuel rod using Monte Carlo method

Pirouzmand, Ahmad, Roosta, Fatemeh

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 4.70 MB

english, 2016

19

Implementation of the batch composition preserving genetic algorithm for burn up extension of a typical PWR

Ilyas, Muhammad, Rauff, Abdul, Zia, Muhammad Gulfam, Ahmad, Siraj-ul-Islam, Ahmad, Masroor

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.04 MB

english, 2016

20

Calculation of six-group importance weighted delayed neutron fractions and prompt neutron lifetime of MTR research reactors based on Monte Carlo method

Arkani, Mohammad, Hassanzadeh, Mostafa, Khakshournia, Samad

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.83 MB

english, 2016

21

Modeling analyses of radioactive aerosol flow and collection in mesoscopic impactor filters

Niu, Fenglei, Du, Xiaochao, Qi, Houbo, Yi, Mingqiang, Yang, Xu

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.74 MB

english, 2016

22

Nuclear energy, renewable energy, CO2 emissions, and economic growth for nine developed countries: Evidence from panel Granger causality tests

Saidi, Kais, Ben Mbarek, Mounir

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 331 KB

english, 2016

23

PWR few-group constants parameterization analysis

Li, Yunzhao, Gao, Shengnan, Wu, Hongchun, Cao, Liangzhi, Shen, Wei

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 12.59 MB

english, 2016

24

A causal model explaining Chinese university students' acceptance of nuclear power

Wang, Yongxiang, Li, Jingping

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1020 KB

english, 2016

25

Considerations for severe accident management under extended station blackout conditions in nuclear power plants

Park, Jong Woon, Seol, Wook-Cheol

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.08 MB

english, 2016

26

Modeling and simulation of radio-iodine released inside the containment as result of an accident

Mehboob, Khurram, Aljohani, Mohammad S.

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.96 MB

english, 2016

27

Forced convection condensation in the presence of noncondensable gas in a horizontal tube; experimental and theoretical study

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

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.35 MB

english, 2016

28

Implicitly solving phase appearance and disappearance problems using two-fluid six-equation model

Zou, Ling, Zhao, Haihua, Zhang, Hongbin

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.64 MB

english, 2016

29

Drying kinetics of thorium oxalate: Experimental investigation and modeling

Beigi, Sadegh, Sobati, Mohammad Amin, Charkhi, Amir

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 771 KB

english, 2016

30

3D in-core fuel management optimization for breed-and-burn reactors

Hou, Jason (Jia), Qvist, Staffan, Kellogg, Roger, Greenspan, Ehud

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.77 MB

english, 2016

31

Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient

Li, Yu Quan, Chang, Hua Jian, Ye, Zi Shen, Fang, Fang Fang, Shi, Yan, Yang, Kai, Cui, Ming Tao

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 7.98 MB

english, 2016

32

Estimation of the fast neutron fluence in Laguna Verde RPV-Steel specimens simulating their irradiation in a TRIGA reactor

Galicia-Aragón, Juan, François-Lacouture, Juan Luis, Aguilar-Hernández, Fortunato

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.41 MB

english, 2016

33

On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology

Alhassan, E., Sjöstrand, H., Helgesson, P., Österlund, M., Pomp, S., Koning, A.J., Rochman, D.

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 985 KB

english, 2016

34

Editorial Board

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 43 KB

english, 2016

35

Preliminary safety analysis on loss of flow accidents and external source transients for LBE cooled ADSR core

Lu, Tianyu, Shan, Jianqiang, Gou, Junli, Zhang, Bin, Zhang, Bo, Ge, Li, Yuan, Yuan, Yang, Zijiang

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 1.04 MB

english, 2016

36

An evaluation of nuclide release from a trench-type LILW repository

Lee, Youn-Myoung, Choi, Heui-Joo

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.48 MB

english, 2016

37

Composition, decomposition and analysis of reactor antineutrino and electron spectra based on gross theory of β-decay and summation method

Yoshida, Tadashi, Tachibana, Takahiro, Hagura, Naoto, Chiba, Satoshi

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 883 KB

english, 2016

38

An approach based on Support Vector Machines and a K-D Tree search algorithm for identification of the failure domain and safest operating conditions in nuclear systems

Di Maio, Francesco, Bandini, Alessandro, Zio, Enrico, Alfonsi, Andrea, Rabiti, Cristian

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 3.22 MB

english, 2016

39

Adaptive burnup stepsize selection using control theory for 2-D lattice depletion simulations

Walter, Daniel J., Manera, Annalisa

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.65 MB

english, 2016

40

Effect of compensation error in drift-flux parameters on predictions of thermal-hydraulic parameters in nuclear safety system analysis codes

Ozaki, Tetsuhiro, Tsukamoto, Naofumi, Nakamura, Ryosuke, Miyaji, Takamasa, Suzuki, Riichiro, Hibiki, Takashi

Journal:

Progress in Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.19 MB

english, 2016

To build up a library is to create a life. It’s never just a random collection of books.

— Carlos María Domínguez

Official channel

Z-Library Desktop Launcher

Tor version

Z-Library

Z-Library Since 2009 support@z-lib.do

EnglishРусскийEspañolItalianoελληνικάاللغة العربيةBahasa IndonesiaBahasa Malaysiaहिन्दीDeutschFrançaisPortuguêsУкраїнськаPolski中文繁體中文日本語Tiếng ViệtAzərbaycan DiliՀայոց լեզուภาษาไทยTürk Diliქართველიবাংলাپښتوతెలుగుاردو한국어SrpskiБългарски