Volume 534

Journal of Nuclear Materials

Volume 534

1

Corrosion behaviour of Al-containing high Cr ferritic oxide dispersion strengthened steel in nitric acid environment

Priya, R., Ningshen, S., Sakairi, M., Ukai, S.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 2.41 MB

2020

2

and

Galvin, C.O.T., Burr, P.A., Cooper, M.W.D., Fossati, P.C.M., Grimes, R.W.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 3.54 MB

2020

3

On residual stress analysis and microstructural evolution for stainless steel type 304 spent nuclear fuel canisters weld joint: Numerical and experimental studies

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 3.39 MB

2020

4

Defect evolution in Ni and solid-solution alloys of NiFe and NiFeCoCr under ion irradiation at 16 and 300Â K

Mieszczynski, C., Ratajczak, R., Jagielski, J., VeliÅa, G., Bei, H., Sales, B.C., Wendler, E., Weber, W.J., Zhang, Y.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 824 KB

2020

5

A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications

Brown, Nicholas R.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 1.41 MB

2020

6

Protection of graphite from salt and gas permeation in molten salt reactors

Lee, Jo Jo, Arregui-Mena, JosÃ© D., Contescu, Cristian I., Burchell, Timothy D., Katoh, Yutai, Loyalka, Sudarshan K.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 5.56 MB

2020

7

Preparation of thorium dioxide nanofibers by electrospinning

Kundrat, Vojtech, Moravec, Zdenek, Pinkas, Jiri

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 1.81 MB

2020

8

Effects of the contents of Al, Ti, W and YO on long-term thermal ageing behavior of 15Cr ODS ferritic steels

Dou, Peng, Sang, Wei, Kimura, Akihiko

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 8.50 MB

2020

9

Ab initio study of He, Ne, Ar, Kr incorporation in zirconium carbide

Sun, Dan, Li, Ruihuan, Ding, Jianhua, Zhang, Pengbo, Zhao, Jijun

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 2.28 MB

2020

10

Microstructure and thermophysical properties of Er2O3-doped UO2 ceramic pellets

Xiao, Hongxing, Long, Chongsheng, Wang, Xiaomin, Chen, Hongsheng, Fan, Shaohua, Yu, Chong, Liu, Guiliang

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 2.98 MB

2020

11

Characterization of the conductivity of metal-oxide interface of zirconium based fuel cladding at low and high burnups

Hawes, Jonathan, Baris, Adrienn, Chiu, Yu-Lung, Abolhassani, Sousan

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 1.89 MB

2020

12

Oxygen potential calculations for conventional and Cr-doped UO2 fuels based on solid solution thermodynamics

Curti, Enzo, Kulik, Dmitrii A.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 2.13 MB

2020

13

Thermal shock fatigue behaviors of various W-0.5Â wt%ZrC materials under repetitive transient heat loads

Wang, M.M., Xie, Z.M., Deng, H.W., Liu, R., Yang, J.F., Zhang, T., Wang, X.P., Fang, Q.F., Liu, C.S., Liu, X., Xiong, Y.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 5.85 MB

2020

14

U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels

Gong, Bowen, Yao, Tiankai, Lei, Penghui, Cai, Lu, Metzger, Kathryn E., Lahoda, Edward J., Boylan, Frank A., Mohamad, Afiqa, Harp, Jason, Nelson, Andrew T., Lian, Jie

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 3.79 MB

2020

15

Effect of He content on microstructure, mechanical properties and He thermal desorption behavior of W film fabricated by RF magnetron sputtering

Wang, Le, Fan, Qunbo, Hao, Ting, Wang, Duoduo, Zhu, Xinjie, Gong, Haichao, Liu, Xin

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 1.77 MB

2020

16

Optimization of the t/10 offset correlation method to obtain the yield strength with the Small Punch Test

Calaf-Chica, Jose, Bravo DÃez, Pedro Miguel, Preciado Calzada, MÃ³nica, Garcia-Tarrago, Maria-Jose

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 2.67 MB

2020

17

Experimental assessment of antimony (Sb) in pure uranium for immobilizing fission product lanthanides

Zhuo, Weiqian, Xie, Yi, Benson, Michael T., Wu, Huali, Mariani, Robert D., Zhang, Jinsuo

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 4.04 MB

2020

18

Gas-solid reaction pathway for chlorination of rare earth and actinide metals using hydrogen and chlorine gas

Okabe, Parker, Newton, Matthew, Rappleye, Devin, Simpson, Michael F.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 4.12 MB

2020

19

Experimental validation of tensile properties measured with thick samples taken from MEGAPIE target

Saito, Shigeru, Suzuki, Kazuhiro, Hatakeyama, Yuichi, Suzuki, Miho, Dai, Yong

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 5.10 MB

2020

20

Corrigendum to âA high temperature W2BâW composite for fusion reactor shieldingâ [J. Nucl. Mater. 532 (2020) 152062]

Athanasakis, Michail, Ivanov, Eugene, Rio, Eduardo del, Humphry-Baker, Samuel A.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 337 KB

2020

21

Editorial Board

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 402 KB

2020

22

Results of the QUENCH-LOCA experimental program at KIT

Stuckert, J., Grosse, M., Steinbrueck, M., Walter, M., Wensauer, A.

Journal:

Journal of Nuclear Materials

Year:

2020

File:

PDF, 8.43 MB

2020

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