Volume 515

Journal of Nuclear Materials

Volume 515

1

Influence of tensile stress on hysteresis loop of Reduced Activation Ferrite & Martensitic steel

Xie, Zheng, Zhao, Yingsong, Bai, Peigen, Li, Qun, Pei, Cuixiang, Chen, Hongen, Chen, Zhenmao

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.67 MB

english, 2019

2

Redox and volatility of Tc(CO)3+ compounds in waste glass melting

Luksic, Steven A., Kim, Dongsang, Levitskaia, Tatiana, Chatterjee, Sayandev, Lukens, Wayne, Kruger, Albert A.

Journal:

Journal of Nuclear Materials

Year:

2019

File:

PDF, 853 KB

2019

3

Raman microspectroscopy of PuO2 particulate aggregates

Villa-Aleman, Eliel, Bridges, Nicholas J., Shehee, Thomas C., Houk, Amanda L.

Journal:

Journal of Nuclear Materials

Year:

2019

File:

PDF, 1.73 MB

2019

4

Corrosion behavior of CLAM steel weld bead in flowing Pb-Bi at 550 °C

Chen, Gang, Lei, Yucheng, Zhu, Qiang, Ju, Na, Li, Tianqing, Wang, Dan

Journal:

Journal of Nuclear Materials

Year:

2019

File:

PDF, 4.35 MB

2019

5

Irradiation assisted stress corrosion cracking of commercial and advanced alloys for light water reactor core internals

Wang, Mi, Song, Miao, Lear, Calvin R., Was, Gary S.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 7.65 MB

english, 2019

6

A model of gas-induced effective expansion strain for porous carbon materials in irradiation environments

Wei, Hongyang, Jian, Xiaobin, Ding, Shurong

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.42 MB

english, 2019

7

Reduced anisotropic properties of Cold Isostatic Pressed graphite matrix compacts

Yeo, Sunghwan, Lee, Young-Woo

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 18.77 MB

english, 2019

8

Crevice corrosion behavior of Alloy 690 in high-temperature water

Ning, Fangqiang, Wu, Xinqiang, Tan, Jibo

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 4.51 MB

english, 2019

9

Investigation of corrosion-erosion behavior of stainless steel considering SS-B4C melt

Sumita, Takehiro, Kobayashi, Yoshinao

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.64 MB

english, 2019

10

Structural features of ISG borosilicate nuclear waste glasses revealed from high-energy X-ray diffraction and molecular dynamics simulations

Lu, Xiaonan, Ren, Mengguo, Deng, Lu, Benmore, Chris J., Du, Jincheng

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 4.65 MB

english, 2019

11

Investigation of physical and chemical properties for upgraded SAP (SiO2Al2O3P2O5) waste form to immobilize radioactive waste salt

Lee, Ki Rak, Riley, Brian J., Park, Hwan-Seo, Choi, Jung-Hoon, Han, Seung Youb, Hur, Jin-Mok, Peterson, Jacob A., Zhu, Zihua, Schreiber, Daniel K., Kruska, Karen, Olszta, Matthew J.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 5.25 MB

english, 2019

12

Characterization of ferroniobium topologically close-packed phase inclusion in nickel-based 152 cladding of dissimilar metal welds

Li, Yifeng, Wang, Jianqiu, Han, En-Hou

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 4.08 MB

english, 2019

13

Direct synthesis of pure brannerite UTi2O6

Mesbah, Adel, Szenknect, Stéphanie, Clavier, Nicolas, Lin, Hantao, Baron, Fabien, Beaufort, Daniel, Batonneau, Yann, Mercadier, Julien, Eglinger, Aurélien, Turuani, Marion, Goncalves, Philippe, Choule

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 1.14 MB

english, 2019

14

Kinetics of oxyapatite [Ca2Nd8(SiO4)6O2] and powellite [(Ca,Sr,Ba)MoO4] dissolution in glass-ceramic nuclear waste forms in acidic, neutral, and alkaline conditions

Neeway, James J., Asmussen, R. Matthew, McElroy, Erin M., Peterson, Jacob A., Riley, Brian J., Crum, Jarrod V.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.27 MB

english, 2019

15

A solution to FIB induced artefact hydrides in Zr alloys

Hanlon, S.M., Persaud, S.Y., Long, F., Korinek, A., Daymond, M.R.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.97 MB

english, 2019

16

Network percolation using a two-species included phase model to predict fission gas accommodation and venting

Prudil, Andrew Albert, Thomas, Evan Stephen, Welland, Michael Joshua

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.79 MB

english, 2019

17

Effect of annealing on mechanical properties and microstructure evolution of borated stainless steels

Won, Chi-Hyoung, Jang, Jae Hoon, Kim, Sung-Dae, Moon, Joonoh, Ha, Heon-Young, Kang, Jun-Yun, Lee, Chang-Hoon, Lee, Tae-Ho, Kang, Namhyun

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 5.22 MB

english, 2019

18

Mechanical properties of irradiated U Mo alloy fuel

Schulthess, Jason L., Lloyd, Wilson R., Rabin, Barry, Wheeler, Katelyn, Walters, Thomas W.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.07 MB

english, 2019

19

Effect of pre-oxidation temperature on the ductility of a zirconium alloy cladding under simulated accident conditions

Lee, Cheol Min, Lee, Hee-Jae, Kim, Hyun-Gil, Mok, Yong-Kyoon, Han, Young-Soo, Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 4.56 MB

english, 2019

20

Ion-irradiation hardening and microstructural evolution in F82H and ferritic alloys

Gao, Jin, Yabuuchi, Kiyohiro, Kimura, Akihiko

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.29 MB

english, 2019

21

Vitrification of an intermediate level Magnox sludge waste

Tan, Shengheng, Kirk, Nick, Marshall, Martyn, McGann, Owen, Hand, Russell J.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.68 MB

english, 2019

22

Differential interplay between Ce and U on local structures of U1-xCexO2 solid solutions probed by X-ray absorption spectroscopy

Cao, Hanjie, Bao, Hongliang, Lin, Xiao, Lin, Jian, Zhang, Linjuan, Huang, Yuying, Wang, Jian-Qiang

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 3.36 MB

english, 2019

23

Dynamics of temperature fields during Wigner energy release in bulk graphite irradiated at low temperature

Pavliuk, A.O., Kotlyarevsky, S.G., Bespala, E.V., Novoselov, I. Yu

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 2.09 MB

english, 2019

24

Postirradiation Examination of FUTURIX-FTA metallic alloy experiments

Harp, Jason M., Capriotti, Luca, Chichester, Heather J.M.

Journal:

Journal of Nuclear Materials

Year:

2019

Language:

english

File:

PDF, 5.73 MB

english, 2019

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