Journal of Nuclear Materials

1

Corrosion behavior of a ferritic/martensitic steel HCM12A exposed to harsh environments

L. Tan, M.T. Machut, K. Sridharan, T.R. Allen

Journal:

Year:

2007

Language:

english

File:

PDF, 2.06 MB

english, 2007

2

Embrittlement of RPV steels: An atom probe tomography perspective

M.K. Miller, K.F. Russell

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 3.90 MB

english, 2007

3

Ferritic/martensitic steels for next-generation reactors

R.L. Klueh, A.T. Nelson

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 1.31 MB

english, 2007

4

The temperature dependence of the yield stress for neutron-irradiated molybdenum

Meimei Li, T.S. Byun, N. Hashimoto, L.L. Snead, S.J. Zinkle

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 309 KB

english, 2007

5

Effect of irradiation on stress corrosion cracking in supercritical water

S. Teysseyre, Z. Jiao, E. West, G.S. Was

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 1.21 MB

english, 2007

6

Time dependence of corrosion in steels for use in lead-alloy cooled reactors

McLean Machut, Kumar Sridharan, Ning Li, Shigeharu Ukai, Todd Allen

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 842 KB

english, 2007

7

Gas-cooled fast reactor fuel fabrication

Randall Fielding, Mitch Meyer, Jan-Fong Jue, Jian Gan

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 762 KB

english, 2007

8

Design challenges for sodium cooled fast reactors

Mamoru Konomura, Masakazu Ichimiya

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 1.63 MB

english, 2007

9

Fuel development for gas-cooled fast reactors

M.K. Meyer, R. Fielding, J. Gan

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 127 KB

english, 2007

10

Thermomechanics of candidate coatings for advanced gas reactor fuels

A. Nosek, J. Conzen, H. Doescher, C. Martin, J. Blanchard

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 642 KB

english, 2007

11

Handbook of SiC properties for fuel performance modeling

Lance L. Snead, Takashi Nozawa, Yutai Katoh, Thak-Sang Byun, Sosuke Kondo, David A. Petti

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 3.06 MB

english, 2007

12

Corrosion and stress corrosion cracking in supercritical water

G.S. Was, P. Ampornrat, G. Gupta, S. Teysseyre, E.A. West, T.R. Allen, K. Sridharan, L. Tan, Y. Chen, X. Ren, C. Pister

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 5.84 MB

english, 2007

13

Oxidation of 9Cr oxide dispersion strengthened steel exposed in supercritical water

Yun Chen, Kumar Sridharan, Shigeharu Ukai, Todd R. Allen

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 2.33 MB

english, 2007

14

The effect of neutron irradiation damage on the properties of grade NBG-10 graphite

Timothy D. Burchell, Lance L. Snead

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 260 KB

english, 2007

15

Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water

Pantip Ampornrat, Gary S. Was

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 1.66 MB

english, 2007

16

Facility for stress corrosion cracking of irradiated specimens in supercritical water

S. Teysseyre, Q. Peng, C. Becker, G.S. Was

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 944 KB

english, 2007

17

Modelling of advanced structural materials for GEN IV reactors

M. Samaras, W. Hoffelner, M. Victoria

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 878 KB

english, 2007

18

An EBSD investigation on flow localization and microstructure evolution of 316L stainless steel for Gen IV reactor applications

Xianglin Wu, Xiao Pan, James C. Mabon, Meimei Li, James F. Stubbins

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 1.42 MB

english, 2007

19

Irradiation tests of mixed-oxide fuel prepared with weapons-derived plutonium

L.J. Ott, R.N. Morris

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 2.25 MB

english, 2007

20

Editorial board

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 17 KB

english, 2007

21

Subject index

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 74 KB

english, 2007

22

Conference Title Page

Journal:

Journal of Nuclear Materials

Year:

2007

File:

PDF, 32 KB

2007

23

Manuscript received date

Journal:

Journal of Nuclear Materials

Year:

2007

File:

PDF, 9 KB

2007

24

Effect of thermomechanical processing on grain boundary character distribution of a Ni-based superalloy

L. Tan, K. Sridharan, T.R. Allen

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 449 KB

english, 2007

26

Foreword

Lance L. Snead

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 63 KB

english, 2007

27

Evaluation of neutron irradiated silicon carbide and silicon carbide composites

George Newsome, Lance L. Snead, Tatsuya Hinoki, Yutai Katoh, Dominic Peters

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 701 KB

english, 2007

28

Fuels for sodium-cooled fast reactors: US perspective

Douglas C. Crawford, Douglas L. Porter, Steven L. Hayes

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 301 KB

english, 2007

29

Shear properties at the PyC/SiC interface of a TRISO-coating

T. Nozawa, L.L. Snead, Y. Katoh, J.H. Miller

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 443 KB

english, 2007

30

The challenges associated with high burnup, high temperature and accelerated irradiation for TRISO-coated particle fuel

John T. Maki, David A. Petti, Darrell L. Knudson, Gregory K. Miller

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 977 KB

english, 2007

31

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Arthur T. Motta, Aylin Yilmazbayhan, Marcelo J. Gomes da Silva, Robert J. Comstock, Gary S. Was, Jeremy T. Busby, Eric Gartner, Qunjia Peng, Yong Hwan Jeong, Jeong Yong Park

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 992 KB

english, 2007

32

Thermophysical characterization of nitrides inert matrices: Preliminary results on zirconium nitride

A. Ciriello, V.V. Rondinella, D. Staicu, J. Somers

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 413 KB

english, 2007

33

An approach to fuel development and qualification

Douglas C. Crawford, Douglas L. Porter, Steven L. Hayes, Mitchell K. Meyer, David A. Petti, Kemal Pasamehmetoglu

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 165 KB

english, 2007

34

Author index

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 69 KB

english, 2007

Volume 371; Issue 1-3

Corrosion behavior of a ferritic/martensitic steel HCM12A exposed to harsh environments

Embrittlement of RPV steels: An atom probe tomography perspective

Ferritic/martensitic steels for next-generation reactors

The temperature dependence of the yield stress for neutron-irradiated molybdenum

Effect of irradiation on stress corrosion cracking in supercritical water

Time dependence of corrosion in steels for use in lead-alloy cooled reactors

Gas-cooled fast reactor fuel fabrication

Design challenges for sodium cooled fast reactors

Fuel development for gas-cooled fast reactors

Thermomechanics of candidate coatings for advanced gas reactor fuels

Handbook of SiC properties for fuel performance modeling

Corrosion and stress corrosion cracking in supercritical water

Oxidation of 9Cr oxide dispersion strengthened steel exposed in supercritical water

The effect of neutron irradiation damage on the properties of grade NBG-10 graphite

Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water

Facility for stress corrosion cracking of irradiated specimens in supercritical water

Modelling of advanced structural materials for GEN IV reactors

An EBSD investigation on flow localization and microstructure evolution of 316L stainless steel for Gen IV reactor applications

Irradiation tests of mixed-oxide fuel prepared with weapons-derived plutonium

Editorial board

Subject index

Conference Title Page

Manuscript received date

Contents

Effect of thermomechanical processing on grain boundary character distribution of a Ni-based superalloy

Foreword

Evaluation of neutron irradiated silicon carbide and silicon carbide composites

Fuels for sodium-cooled fast reactors: US perspective

Shear properties at the PyC/SiC interface of a TRISO-coating

The challenges associated with high burnup, high temperature and accelerated irradiation for TRISO-coated particle fuel

Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

Thermophysical characterization of nitrides inert matrices: Preliminary results on zirconium nitride

An approach to fuel development and qualification

Author index