Volume 524

Journal of Nuclear Materials

Volume 524

1

Equation of state and strain-induced stabilization of δ-phase stabilized plutonium alloys

Zhang, Jianzhong, Freibert, Franz J., Clausen, Bjorn, Smith, Alice I., Vogel, Sven C., Brown, Donald W.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.02 MB

english, 2019

2

The correlation between tetragonal phase and the undulated metal/oxide interface in the oxide films of zirconium alloys

Liao, Jingjing, Yang, Zhongbo, Qiu, Shaoyu, Peng, Qian, Li, Zhengcao, Zhang, Junsong

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.03 MB

english, 2019

3

Electronic structure, elastic and thermal transport properties of thorium monocarbide based on first-principles study

Wang, Hao, Lan, Jun-Qing, Hu, Cui-E., Chen, Xiang-Rong, Geng, Hua-Yun

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.63 MB

english, 2019

4

Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor

Lee, Jo Jo, Raiman, Stephen S., Katoh, Yutai, Koyanagi, Takaaki, Contescu, Cristian I., Hu, Xunxiang, Yang, Ying

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.18 MB

english, 2019

5

Corrosion resistance and microstructural stability of austenitic Fe–Cr–Al–Ni model alloys exposed to oxygen-containing molten lead

Shi, Hao, Jianu, Adrian, Weisenburger, Alfons, Tang, Chongchong, Heinzel, Annette, Fetzer, Renate, Lang, Fabian, Stieglitz, Robert, Müller, Georg

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 4.44 MB

english, 2019

6

Investigation on the structures of τ1 and τ2 compounds in the Zr–Fe–Cu system and phase equilibria of the Zr–Nb–Fe–Cu system

Chang, Pei-Lin, Zou, Nan, Wang, Jing-Jing, Shen, Jian-Yun, Lu, Xiao-Gang

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.44 MB

english, 2019

7

Variance-based sensitivity analysis applied to hydrogen migration and redistribution model in Bison. Part I: Simulation of historical experiments

Aly, Zineb, Casagranda, Albert, Pastore, Giovanni, Brown, Nicholas R.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.76 MB

english, 2019

8

Understanding of electrochemical behaviors of niobium in molten LiCl–KCl eutectic for pyrochemical decontamination process

Jeong, Gwan Yoon, Sohn, Sungjune, Jeon, Younghwan, Park, Jaeyeong

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 5.07 MB

english, 2019

9

Characterization of solid fission products in 13.7% FIMA MOX fuel using electron microscopy techniques

Parrish, Riley J., Wright, Karen E., Winston, Alexander J., McKinney, Casey, Harp, Jason M., Aitkaliyeva, Assel

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.90 MB

english, 2019

10

Shear strength of nanocrystalline δ-phase Pu-Ga alloys: Atomistic simulations

Karavaev, A.V., Dremov, V.V., Sapozhnikov, F.A.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 7.98 MB

english, 2019

11

Investigation of the on-site Coulomb correction and temperature dependence of the stability of U–Si phases using DFT+U

Kocevski, V., Lopes, D.A., Besmann, T.M.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.37 MB

english, 2019

12

The effect of dislocations on irradiation-induced vacancy-like defects in FeCu alloy and reactor pressure vessel steel

Liu, Hailong, Wang, Xiaoyang, Cui, Wei, Li, Qiulin, Xu, Ben, Liu, Wei, Shu, Guogang

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.05 MB

english, 2019

13

Fabrication and characteristics of lithium metatitanate tritium breeder via polymer-assisted sedimentation method under different sintering conditions

Lu, Wei, Pu, Wenjing, Chu, Delin, Yang, Jinhong, He, Shengnan, Li, Kaiping, Wang, Weihua

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.38 MB

english, 2019

14

Effects of neutron irradiation on 12Cr–6Al-ODS steel with electron-beam weld line

Gao, Jin, Song, Peng, Huang, Yen-Jui, Yabuuchi, Kiyohiro, Kimura, Akihiko, Sakamoto, Kan, Yamashita, Shinichiro

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.75 MB

english, 2019

15

The adsorption and dissolution properties of iron surfaces in liquid lithium and lead under a fusion environment

Xu, Yichun, Zhang, Yange, Li, Xiangyan, Liu, Wei, Liu, C.S., Fang, Qianfeng, Deng, Huiqiu, Wang, Zhiguang

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.83 MB

english, 2019

16

The effect of pressure on hydrogen solubility in Zircaloy-4

Weekes, H.E., Dye, D., Proctor, J.E., Smith, D., Simionescu, C., Prior, T.J., Wenman, M.R.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.38 MB

english, 2019

17

In-situ HVEM observation under 2 MeV electron irradiations on Y–Ti–O nanoparticles in 12Cr-ODS steel at 723K

Oh, Sun-Ryung, Kano, Sho, Yang, Huilong, McGrady, John, Yasuda, Hidehiro, Abe, Hiroaki

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.17 MB

english, 2019

18

Texture evolution of cold-rolled Zr-1Sn-0.3Nb-0.3Fe-0.1Cr alloy during annealing

Chen, Jing, Jiang, Yilan, Liu, Huiqun, Yi, Danqing, Zhang, Ruiqian, Dai, Xun, Liu, Shaoqiang

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 5.92 MB

english, 2019

19

Ferromagnetic effects on non-Arrhenius diffusion of single interstitial helium solute in BCC Fe

Lai, Kan, Wen, Haohua, Liu, Jianyi, Wu, Yifeng, Zheng, Yue

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.44 MB

english, 2019

20

The effect of nitride formation on the oxidation kinetics of Zry-4 fuel cladding under steam-air atmospheres at 1273–1573 K

Negyesi, Martin, Amaya, Masaki

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.01 MB

english, 2019

21

Corrosion resistance and microstructural stability of austenitic Fe–Cr–Al–Ni model alloys exposed to oxygen-containing molten lead

Shi, Hao, Jianu, Adrian, Weisenburger, Alfons, Tang, Chongchong, Heinzel, Annette, Fetzer, Renate, Lang, Fabian, Stieglitz, Robert, Müller, Georg

Journal:

Journal of Nuclear Materials

Year:

2019

File:

PDF, 4.44 MB

2019

22

The effect of dislocations on irradiation-induced vacancy-like defects in FeCu alloy and reactor pressure vessel steel

Liu, Hailong, Wang, Xiaoyang, Cui, Wei, Li, Qiulin, Xu, Ben, Liu, Wei, Shu, Guogang

Journal:

Journal of Nuclear Materials

Year:

2019

File:

PDF, 3.05 MB

2019

23

Effects of UMo irradiation creep on the thermo-mechanical behavior in monolithic UMo/Al fuel plates

Yan, Feng, Jian, Xiaobin, Ding, Shurong

Journal:

Journal of Nuclear Materials

Year:

2019

File:

PDF, 2.52 MB

2019

24

Damage mechanics modeling of the non-linear behavior of SiC/SiC ceramic matrix composite fuel cladding

Alabdullah, Mohammad, Ghoniem, Nasr M.

Journal:

Journal of Nuclear Materials

Year:

2019

File:

PDF, 5.04 MB

2019