Volume 487

Journal of Nuclear Materials

Volume 487

1

Engineered nano-magnetic iron oxide-urea-activated carbon nanolayer sorbent for potential removal of uranium (VI) from aqueous solution

Mahmoud, Mohamed E., Khalifa, Mohamed A., El Wakeel, Yasser M., Header, Mennatllah S., Abdel-Fattah, Tarek M.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 736 KB

english, 2017

2

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy

Harte, Allan, Topping, M., Frankel, P., Jädernäs, D., Romero, J., Hallstadius, L., Darby, E.C., Preuss, M.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.29 MB

english, 2017

3

Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions

Aydogan, E., Chen, T., Gigax, J.G., Chen, D., Wang, X., Dzhumaev, P.S., Emelyanova, O.V., Ganchenkova, M.G., Kalin, B.A., Leontiva-Smirnova, M., Valiev, R.Z., Enikeev, N.A., Abramova, M.M., Wu, Y., Lo

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 10.56 MB

english, 2017

4

Effect of Na 2 O on aqueous dissolution of nuclear waste glasses

Farooqi, Rahmat Ullah, Hrma, Pavel

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 542 KB

english, 2017

5

A semi-empirical model for the formation and depletion of the high burnup structure in UO 2

Pizzocri, D., Cappia, F., Luzzi, L., Pastore, G., Rondinella, V.V., Van Uffelen, P.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.09 MB

english, 2017

6

A stochastic XFEM model for the tensile strength prediction of heterogeneous graphite based on microstructural observations

Bansal, Manik, Singh, I.V., Mishra, B.K., Sharma, Kamal, Khan, I.A.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 4.91 MB

english, 2017

7

Radiation stable, hybrid, chemical vapor infiltration/preceramic polymer joining of silicon carbide components

Khalifa, Hesham E., Koyanagi, Takaaki, Jacobsen, George M., Deck, Christian P., Back, Christina A.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.09 MB

english, 2017

8

Comparative study of displacement cascades simulated with ‘magnetic’ potentials and Mendelev-type potential in α-Fe

Gao, Chan, Tian, Dongfeng, Li, Maosheng, Qian, Dazhi

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 621 KB

english, 2017

9

Time of flight measurements of unirradiated and irradiated nuclear graphite under cyclic compressive load

Bodel, W., Atkin, C., Marsden, B.J.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 8.54 MB

english, 2017

10

High temperature nanoindentation hardness and Young's modulus measurement in a neutron-irradiated fuel cladding material

Kese, K., Olsson, P.A.T., Alvarez Holston, A.-M., Broitman, E.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 836 KB

english, 2017

11

Deuterium implantation into Y 2 O 3 -doped and pure tungsten: Deuterium retention and blistering behavior

Zhao, M., Jacob, W., Manhard, A., Gao, L., Balden, M., von Toussaint, U., Zhou, Z.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.29 MB

english, 2017

12

Strong trapping and slow diffusion of helium in a tungsten grain boundary

Wang, Xin-Xin, Niu, Liang-Liang, Wang, Shaoqing

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.96 MB

english, 2017

13

Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels

Newell, Ryan, Park, Youngjoo, Mehta, Abhishek, Keiser, Dennis, Sohn, Yongho

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 30.97 MB

english, 2017

14

Physical properties of core-concrete systems: Al 2 O 3 -ZrO 2 molten materials measured by aerodynamic levitation

Ohishi, Yuji, Kargl, F., Nakamori, F., Muta, Hiroaki, Kurosaki, Ken, Yamanaka, Shinsuke

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 985 KB

english, 2017

15

Preparation and characterization of Al 2 O 3 coating by MOD method on CLF-1 RAFM steel

Wang, L., Yang, J.J., Feng, Y.J., Li, F.Z., Liao, J.L., Yang, Y.Y., Feng, K.M., Liu, N.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 5.59 MB

english, 2017

16

Tritium trapping states induced by lithium-depletion in Li 2 TiO 3

Kobayashi, Makoto, Oya, Yasuhisa, Okuno, Kenji

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.04 MB

english, 2017

17

Migration and nucleation of helium atoms at (110) twist grain boundaries in tungsten

Feng, Ya-Xin, Shang, Jia-Xiang, Lu, Guang-Hong

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.75 MB

english, 2017

18

Phase diagram of the Fe-Sn-Zr system at 800 °C

Nieva, N., Corvalán, C., Jiménez, M.J., Gómez, A., Arreguez, C., Joubert, J.-M., Arias, D.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.52 MB

english, 2017

19

Oxygen potentials, oxygen diffusion coefficients and defect equilibria of nonstoichiometric (U,Pu)O 2±x

Kato, Masato, Watanabe, Masashi, Matsumoto, Taku, Hirooka, Shun, Akashi, Masatoshi

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 819 KB

english, 2017

20

Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel

Jeong, G.Y., Kim, Yeon Soo, Jamison, L.M., Robinson, A.B., Lee, K.H., Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 3.20 MB

english, 2017

21

A novel way to estimate the nanoindentation hardness of only-irradiated layer and its application to ion irradiated Fe-12Cr alloy

Kim, Hoon-Seop, Lee, Dong-Hyun, Seok, Moo-Young, Zhao, Yakai, Kim, Woo-Jin, Kwon, Dongil, Jin, Hyung-Ha, Kwon, Junhyun, Jang, Jae-il

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 778 KB

english, 2017

22

TEM study on the initial oxidation of Zircaloy-4 thin foil specimens heated in a low vacuum air condition at 280–300 °C

Wang, Zhen, Zhou, Bang-xin, Zhu, Wei, Wen, Bang, Yao, Mei-yi, Li, Qiang, Wu, Lu, Zhang, Jin-long, Fang, Zhong-qiang

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.94 MB

english, 2017

23

Effects of He radiation on cavity distribution and hardness of bulk nanolayered Cu-Nb composites

Yang, L.X., Zheng, S.J., Zhou, Y.T., Zhang, J., Wang, Y.Q., Jiang, C.B., Mara, N.A., Beyerlein, I.J., Ma, X.L.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 10.94 MB

english, 2017

24

Impurity diagnosis of a KSTAR graphite divertor tile using laser induced breakdown spectroscopy technique

Kim, Minju, Cho, Min Sang, Cho, Byoung Ick

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.09 MB

english, 2017

25

Surface damage of W exposed to combined stationary D plasma and ELMs-like pulsed plasma

Jia, Y.Z., Liu, W., Xu, B., Qu, S.L., Morgan, T.W.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.77 MB

english, 2017

26

Oxidation and reduction behaviors of a prototypic MgO-PuO 2-x inert matrix fuel

Miwa, Shuhei, Osaka, Masahiko

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 613 KB

english, 2017

27

Studies on the phase diagram of Bi-Cr-O system

Meera, A.V., Basu, Joysurya, Ganesan, Rajesh, Gnanasekaran, T.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.54 MB

english, 2017

28

Influence of neutron irradiation on the microstructure of nuclear graphite: An X-ray diffraction study

Zhou, Z., Bouwman, W.G., Schut, H., van Staveren, T.O., Heijna, M.C.R., Pappas, C.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.60 MB

english, 2017

29

Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions

Yano, Y., Tanno, T., Oka, H., Ohtsuka, S., Inoue, T., Kato, S., Furukawa, T., Uwaba, T., Kaito, T., Ukai, S., Oono, N., Kimura, A., Hayashi, S., Torimaru, T.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 4.32 MB

english, 2017

30

Influence of grain growth on the structural properties of the nanocrystalline Gd 2 Ti 2 O 7

Kulriya, P.K., Yao, Tiankai, Scott, Spencer Michael, Nanda, Sonal, Lian, Jie

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 13.90 MB

english, 2017

31

Production, microstructure and mechanical properties of two different austenitic ODS steels

Gräning, T., Rieth, M., Hoffmann, J., Möslang, A.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 6.34 MB

english, 2017

32

Hydrogen absorption in U 3 Si 2 and its impact on electronic properties

Mašková, Silvie, Miliyanchuk, Khrystyna, Havela, Ladislav

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 647 KB

english, 2017

33

Effect of external stress on deuteride (hydride) precipitation in Zircaloy-4 using in situ neutron diffraction

Lin, Jun-li, An, Ke, Stoica, Alexandru D., Heuser, Brent J.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.45 MB

english, 2017

34

Chemical compatibility between UO 2 fuel and SiC cladding for LWRs. Application to ATF (Accident-Tolerant Fuels)

Braun, James, Guéneau, Christine, Alpettaz, Thierry, Sauder, Cédric, Brackx, Emmanuelle, Domenger, Renaud, Gossé, Stéphane, Balbaud-Célérier, Fanny

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 4.52 MB

english, 2017

35

Hydrogen trapping at divacancies and impurity-vacancy complexes in nickel: First principles study

Subashiev, Arsen V., Nee, Han H.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 6.05 MB

english, 2017

36

First principles study of inert-gas (helium, neon, and argon) interactions with hydrogen in tungsten

Kong, Xiang-Shan, Hou, Jie, Li, Xiang-Yan, Wu, Xuebang, Liu, C.S., Chen, Jun-Ling, Luo, G.-N.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.06 MB

english, 2017

37

Thorium aspartate tetrahydrate precursor to ThO 2 : Comparison of hydrothermal and thermal conversions

Clavier, N., Maynadié, J., Mesbah, A., Hidalgo, J., Lauwerier, R., Nkou Bouala, G.I., Parrès-Maynadié, S., Meyer, D., Dacheux, N., Podor, R.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.17 MB

english, 2017

38

Study on the mechanism of deoxidization and purification for Li 2 BeF 4 molten salt via graphite nanoparticles

Xie, Meng-ya, Li, Li, Ding, Ya-ping, Zhang, Guo-xin

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 977 KB

english, 2017

39

10 B areal density: A novel approach for design and fabrication of B 4 C/6061Al neutron absorbing materials

Li, Yuli, Wang, Wenxian, Zhou, Jun, Chen, Hongsheng, Zhang, Peng

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 3.90 MB

english, 2017

40

Thermodynamic studies on charge-coupled substituted synthetic monazite

Rawat, D., Phapale, S., Mishra, R., Dash, S.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.97 MB

english, 2017

41

An XPS study on the impact of relative humidity on the aging of UO 2 powders

Donald, Scott B., Dai, Zurong R., Davisson, M. Lee, Jeffries, Jason R., Nelson, Art J.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.52 MB

english, 2017

42

Formation of solid thorium monoxide at near-ambient conditions as observed by neutron reflectometry and interpreted by screened hybrid functional calculations

He, Heming, Majewski, Jaroslaw, Allred, David D., Wang, Peng, Wen, Xiaodong, Rector, Kirk D.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.32 MB

english, 2017

43

Development of first ever scanning probe microscopy capabilities for plutonium

Beaux, Miles F., Cordoba, Miguel Santiago, Zocco, Adam T., Vodnik, Douglas R., Ramos, Michael, Richmond, Scott, Moore, David P., Venhaus, Thomas J., Joyce, Stephen A., Usov, Igor O.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.66 MB

english, 2017

44

Structure and short time degradation studies of sodium zirconium phosphate ceramics loaded with simulated fast breeder (FBR) waste

Ananthanarayanan, A., Ambashta, R.D., Sudarsan, V., Ajithkumar, T., Sen, D., Mazumder, S., Wattal, P.K.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.52 MB

english, 2017

45

Obtention of the constitutive equation of hydride blisters in fuel cladding from nanoindentation tests

Martin Rengel, M.A., Gomez, F.J., Rico, A., Ruiz-Hervias, J., Rodriguez, J.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.54 MB

english, 2017

46

Effect of reactor radiation on the thermal conductivity of TREAT fuel

Mo, Kun, Miao, Yinbin, Kontogeorgakos, Dimitrios C., Connaway, Heather M., Wright, Arthur E., Yacout, Abdellatif M.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.92 MB

english, 2017

47

The corrosion behavior of CVI SiC matrix in SiC f /SiC composites under molten fluoride salt environment

Wang, Hongda, Feng, Qian, Wang, Zhen, Zhou, Haijun, Kan, Yanmei, Hu, Jianbao, Dong, Shaoming

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.40 MB

english, 2017

48

Phase evolution and aqueous durability of Zr 1−x−y Ce x Nd y O 2−y/2 ceramics designed to immobilize actinides with multi-valences

Ding, Yi, Long, Xinggui, Peng, Shuming, Zhang, Dong, Tan, Zhaoyi, Lu, Xirui

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.57 MB

english, 2017

49

In situ synchrotron X-ray diffraction study of hydrides in Zircaloy-4 during thermomechanical cycling

Cinbiz, Mahmut N., Koss, Donald A., Motta, Arthur T., Park, Jun-Sang, Almer, Jonathan D.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 2.68 MB

english, 2017

50

Microstructural comparison of effects of hafnium and titanium additions in spark-plasma-sintered Fe-based oxide-dispersion strengthened alloys

Huang, Yina, Zhang, Hongtao, Auger, Maria A., Hong, Zuliang, Ning, Huanpo, Gorley, Michael J., Grant, Patrick S., Reece, Michael J., Yan, Haixue, Roberts, Steve G.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 5.71 MB

english, 2017

51

Application of the rotating cylinder electrode in molten LiCl-KCl eutectic containing uranium(III)- and magnesium(II)-chloride

Rappleye, Devin, Simpson, Michael F.

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 1.50 MB

english, 2017