Volume 451; Issue 1-3

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Journal of Nuclear Materials
Volume 451; Issue 1-3

Journal of Nuclear Materials

Volume 451; Issue 1-3

1

Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in

Andersson, D.A., Garcia, P., Liu, X.-Y., Pastore, G., Tonks, M., Millett, P., Dorado, B., Gaston, D.R., Andrs, D., Williamson, R.L., Martineau, R.C., Uberuaga, B.P., Stanek, C.R.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.61 MB

english, 2014

2

The plutonium–hydrogen reaction: SEM characterization of product morphology

Dinh, L.N., McCall, S.K., Saw, C.K., Haschke, J.M., Allen, P.G., McLean, W.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.38 MB

english, 2014

3

A facility for studying irradiation accelerated corrosion in high temperature water

Raiman, Stephen S., Flick, Alexander, Toader, Ovidiu, Wang, Peng, Samad, Nassim A., Jiao, Zhijie, Was, Gary S.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.98 MB

english, 2014

4

Modeling and analysis of UN TRISO fuel for LWR application using the PARFUME code

Collin, Blaise P.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.64 MB

english, 2014

5

Determination of Gd concentration profile in UO2–Gd2O3 fuel pellets

Tobia, D., Winkler, E.L., Milano, J., Butera, A., Kempf, R., Bianchi, L., Kaufmann, F.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 446 KB

english, 2014

6

Interaction of carbon–vacancy complex with minor alloying elements of ferritic steels

Bakaev, A., Terentyev, D., He, X., Zhurkin, E.E., Van Neck, D.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 784 KB

english, 2014

7

Steady-state dynamical phase diagram calculation of U–Nb binary system under irradiation: Ballistic effect

Liu, X.J., Zhao, Y.L., Lu, Y., Xu, W.W., Jia, J.P., Wang, C.P.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 504 KB

english, 2014

8

Annealing of radiation-induced damage in tungsten under and after irradiation with 20MeV self-ions

Ogorodnikova, O.V., Gasparyan, Yu., Efimov, V., Ciupiński, Ł., Grzonka, J.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.75 MB

english, 2014

9

Comparison of liquid metal solution model predictions with compatibility data of niobium with liquid sodium

Krasin, V.P., Soyustova, S.I.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 283 KB

english, 2014

10

Thermodynamic assessment of the palladium–selenium (Pd–Se) system

Bordier, S., Chocard, A., Gossé, S.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.60 MB

english, 2014

11

Morphological analysis of zirconium nuclear fuel retaining rods braided with SiC: Quality assurance and defect identification

Glazoff, Michael V., Hiromoto, Robert, Tokuhiro, Akira

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.92 MB

english, 2014

12

Effects of Cr and Ni on interdiffusion and reaction between U and Fe–Cr–Ni alloys

Huang, K., Park, Y., Zhou, L., Coffey, K.R., Sohn, Y.H., Sencer, B.H., Kennedy, J.R.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.84 MB

english, 2014

13

Synthesis and structure of Ce1−xEuxPO4 solid solutions for minor actinides immobilization

Wang, Xiaohuan, Teng, Yuancheng, Huang, Yi, Wu, Lang, Zeng, Pan

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.70 MB

english, 2014

14

Mechanochemical synthesis of uranium sesquisilicide

Alanko, Gordon A., Butt, Darryl P.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.37 MB

english, 2014

15

Nanoindentation creep study on an ion beam irradiated oxide dispersion strengthened alloy

Huang, Zijing, Harris, Adrian, Maloy, Stuart A., Hosemann, Peter

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.66 MB

english, 2014

16

Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics

Couet, Adrien, Motta, Arthur T., Comstock, Robert J.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 3.24 MB

english, 2014

17

Cladding oxidation model development based on diffusion equations and a simulation of the monoclinic-tetragonal phase transformation of zirconia during transient oxidation

He, Xiaoqiang, Yu, Hongxing, Jiang, Guangming, Dang, Gaojian, Wu, Dan, Zhang, Yu

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.12 MB

english, 2014

18

Ion flux dependence of atomic hydrogen loss probabilities on tungsten and carbon surfaces

Samuell, C.M., Corr, C.S.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 435 KB

english, 2014

19

TEM characterization of in-reactor neutron irradiated CANDU spacer material Inconel X-750

Zhang, He Ken, Yao, Zhongwen, Morin, Gregory, Griffiths, Malcolm

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 3.33 MB

english, 2014

20

Thermal expansion measurement and heat capacity evaluation of hypo-stoichiometric PuO2.00

Kato, Masato, Uchida, Teppei, Matsumoto, Taku, Sunaoshi, Takeo, Nakamura, Hiroki, Machida, Masahiko

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 419 KB

english, 2014

21

Water adsorption and dissociation on the PuO2(110) surface

Jomard, Gérald, Bottin, François, Geneste, Grégory

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 998 KB

english, 2014

22

Oxide microstructural evolution of Zr–0.7Sn–0.35Nb–0.3Fe alloys containing Ge corroded in lithiated water

Xie, Xingfei, Zhang, Jinlong, Yao, Meiyi, Zhou, Bangxin, Peng, Jianchao, Liang, Xue

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 3.33 MB

english, 2014

23

In situ creep measurements on micropillar samples during heavy ion irradiation

Özerinç, Sezer, Averback, Robert S., King, William P.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.89 MB

english, 2014

24

Influence of free carbon on the characteristics of ZrC and deposition of near-stoichiometric ZrC in TRISO coated particle fuel

Kim, Daejong, Ko, Myeong Jin, Park, Ji Yeon, Cho, Moon Sung, Kim, Weon-Ju

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.20 MB

english, 2014

25

Quantitative atom probe tomography characterization of microstructures in a proton irradiated 304 stainless steel

Chen, Yimeng, Chou, Peter H., Marquis, Emmanuelle A.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.05 MB

english, 2014

26

Slow positron beam and nanoindentation study of irradiation-related defects in reactor vessel steels

Liu, Xiangbing, Wang, Rongshan, Jiang, Jing, Wu, Yichu, Zhang, Chonghong, Ren, Ai, Xu, Chaoliang, Qian, Wangjie

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 593 KB

english, 2014

27

Degradation in steam of 60cm-long B4C control rods

Dominguez, C., Drouan, D.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.71 MB

english, 2014

28

Vanadium diffusion coating on HT-9 cladding for mitigating the fuel cladding chemical interactions

Lo, Wei-Yang, Yang, Yong

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.44 MB

english, 2014

29

Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond

Wiss, Thierry, Hiernaut, Jean-Pol, Roudil, Danièle, Colle, Jean-Yves, Maugeri, Emilio, Talip, Zeynep, Janssen, Arne, Rondinella, Vincenzo, Konings, Rudy J.M., Matzke, Hans-Joachim, Weber, William J.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.15 MB

english, 2014

30

In situ heating TEM analysis of oxide layer formed on Zr–1.5Nb alloy

Kim, Hyun-Gil, Kim, Il-Hyun, Park, Jeong-Yong, Yoo, Seung Jo, Kim, Jin-Gyu

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 3.97 MB

english, 2014

31

Effects of thermal treatment on the mechanical integrity of silicon carbide in HTR fuel up to 2200°C

Rohbeck, Nadia, Xiao, Ping

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.90 MB

english, 2014

32

Oxidation rate of graphitic matrix material in the kinetic regime for VHTR air ingress accident scenarios

Lee, Jo Jo, Ghosh, Tushar K., Loyalka, Sudarshan K.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.15 MB

english, 2014

33

Fabricating high performance tungsten alloys through zirconium micro-alloying and nano-sized yttria dispersion strengthening

Liu, R., Xie, Z.M., Hao, T., Zhou, Y., Wang, X.P., Fang, Q.F., Liu, C.S.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.73 MB

english, 2014

34

Calibration of dimensional change in finite element models using AGR moderator brick measurements

McNally, K., Hall, G., Tan, E., Marsden, B.J., Warren, N.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.86 MB

english, 2014

35

Effect of pressure on f-electron delocalization and oxidation in actinide dioxides

Petit, L., Szotek, Z., Temmerman, W.M., Stocks, G.M., Svane, A.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 923 KB

english, 2014

36

Superior corrosion resistance properties of TiN-based coatings on Zircaloy tubes in supercritical water

Khatkhatay, Fauzia, Jiao, Liang, Jian, Jie, Zhang, Wenrui, Jiao, Zhijie, Gan, Jian, Zhang, Hongbin, Zhang, Xinghang, Wang, Haiyan

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.52 MB

english, 2014

37

Thermoelastoviscoplastic modeling of RAFM steel JLF-1 using tensile and low cycle fatigue experiments

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.04 MB

english, 2014

38

True stress–strain curves of cold worked stainless steel over a large range of strains

Kamaya, Masayuki, Kawakubo, Masahiro

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 4.10 MB

english, 2014

39

Modeling the tension–compression asymmetric yield behavior of β-treated Zircaloy-4

Zhai, Jinyuan, Gao, Xiaosheng, Sobotka, James C., Webler, Bryan A., Cockeram, Brian V.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.16 MB

english, 2014

40

Microstructure examination of Fe–14Cr ODS ferritic steels produced through different processing routes

Oksiuta, Z., Hosemann, P., Vogel, S.C., Baluc, N.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 2.25 MB

english, 2014

41

High-temperature compatibility between liquid metal as PWR fuel gap filler and stainless steel and high-density concrete

Wongsawaeng, Doonyapong, Jumpee, Chayanit, Jitpukdee, Manit

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.72 MB

english, 2014

42

Deuterium implantation into tungsten nitride: Negligible diffusion at 300K

Gao, L., Jacob, W., Schwarz-Selinger, T., Manhard, A.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 406 KB

english, 2014

43

Removal of carbon-14 from irradiated graphite

Dunzik-Gougar, Mary Lou, Smith, Tara E.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 3.32 MB

english, 2014

44

Helium defects interactions and mechanism of helium bubble growth in tungsten: A molecular dynamics simulation

Li, Xiao-Chun, Liu, Yi-Nan, Yu, Yi, Luo, Guang-Nan, Shu, Xiaolin, Lu, Guang-Hong

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.41 MB

english, 2014

45

Mechanical properties of Zr–2.5%Nb pressure tube material subjected to heat treatments in α+β phase field

Kulkarni, R.V., Mani Krishna, K.V., Neogy, S., Srivastava, D., Ramadasan, E., Shriwastaw, R.S., Rath, B.N., Saibaba, N., Jha, S.K., Dey, G.K.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 3.11 MB

english, 2014

46

Implantation of high concentration noble gases in cubic zirconia and silicon carbide: A contrasted radiation tolerance

Velişa, Gihan, Debelle, Aurélien, Thomé, Lionel, Mylonas, Stamatis, Vincent, Laetitia, Boulle, Alexandre, Jagielski, Jacek, Pantelica, Dan

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 3.47 MB

english, 2014

47

Deterioration of yttria-stabilized zirconia by boron carbide alone or mixed with metallic or oxidized Fe, Cr, Zr mixtures

De Bremaecker, A., Ayrault, L., Clément, B.

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 1.78 MB

english, 2014