P. J. Maziasz: search on Z-Library

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1

Heat-treatment effect on impact properties of reduced-activation steels

R.L. Klueh, P.J. Maziasz, D.J. Alexander

Journal:

Journal of Nuclear Materials

Year:

1991

Language:

english

File:

PDF, 1.34 MB

english, 1991

2

Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel

S.J. Zinkle, P.J. Maziasz, R.E. Stoller

Journal:

Journal of Nuclear Materials

Year:

1993

Language:

english

File:

PDF, 2.24 MB

english, 1993

3

Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environment

M.L. Grossbeck, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1979

Language:

english

File:

PDF, 532 KB

english, 1979

4

[ASME ASME 2007 Pressure Vessels and Piping Conference - San Antonio, Texas, USA (July 22–26, 2007)] Volume 9: Eighth International Conference on Creep and Fatigue at Elevated Temperatures - Effects of Long-Term Service on the Microstructure and Tensile Properties of Alloy 800H

Swindeman, Robert W., Zamrik, Sam Y., Maziasz, Phillip J.

Year:

2007

Language:

english

File:

PDF, 781 KB

english, 2007

5

Microstructural development of PCAs irradiated in HFIR at 300 to 400° C

M.P. Tanaka, P.J. Maziasz, A. Hishinuma, S. Hamada

Journal:

Journal of Nuclear Materials

Year:

1986

Language:

english

File:

PDF, 630 KB

english, 1986

6

Reduced-activation ferritic steels: A comparison with CrMo steels

R.L. Klueh, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1988

Language:

english

File:

PDF, 587 KB

english, 1988

7

Temperature dependence of the dislocation microstructure of PCA austenitic stainless steel irradiated in ORR spectrally-tailored experiments

Journal:

Journal of Nuclear Materials

Year:

1992

Language:

english

File:

PDF, 370 KB

english, 1992

8

Overview of microstructural evolution in neutron-irradiated austenitic stainless steels

Journal:

Journal of Nuclear Materials

Year:

1993

Language:

english

File:

PDF, 7.43 MB

english, 1993

9

Void swelling resistance of phosphorus-modified austenitic stainless steels during HFIR irradiation at 300–500°C to 57 dpa

Journal:

Journal of Nuclear Materials

Year:

1993

Language:

english

File:

PDF, 2.26 MB

english, 1993

10

Comprehensive Nuclear Materials || Properties of Austenitic Steels for Nuclear Reactor Applications

Year:

2012

Language:

english

File:

PDF, 2.23 MB

english, 2012

11

Development of Creep-Resistant and Oxidation-Resistant Austenitic Stainless Steels for High Temperature Applications

Maziasz, Philip J.

Journal:

Year:

2017

Language:

english

File:

PDF, 5.18 MB

english, 2017

12

The precipitation response of 20%-cold-worked type 316 stainless steel to simulated fusion irradiation

Journal:

Journal of Nuclear Materials

Year:

1979

Language:

english

File:

PDF, 644 KB

english, 1979

13

Tensile properties of 20% cold-worked titanium-modified type 316 stainless steel irradiated in HFIR

M.L. Grossbeck, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1981

Language:

english

File:

PDF, 591 KB

english, 1981

14

Swelling, microstructural development and helium effects in type 316 stainless steel irradiated in HFIR and EBR-II

P.J. Maziasz, M.L. Grossbeck

Journal:

Journal of Nuclear Materials

Year:

1981

Language:

english

File:

PDF, 700 KB

english, 1981

15

Fission-fusion correlations for swelling and microstructure in stainless steels: Effect of the helium to displacement per atom ratio

G.R. Odette, P.J. Maziasz, J.A. Spitznagel

Journal:

Journal of Nuclear Materials

Year:

1981

Language:

english

File:

PDF, 1.42 MB

english, 1981

16

The impact of swelling on fusion reactor first wall lifetime

R.F. Mattas, F.A. Garner, M.L. Grossbeck, P.J. Maziasz, G.R. Odette, R.E. Stoller

Journal:

Journal of Nuclear Materials

Year:

1984

Language:

english

File:

PDF, 458 KB

english, 1984

17

Improved swelling resistance for PCA austenitic stainless steel under HFIR irradiation through microstructural control

P.J. Maziasz, D.N. Braski

Journal:

Journal of Nuclear Materials

Year:

1984

Language:

english

File:

PDF, 1.80 MB

english, 1984

18

Microstructural design of PCA austenitic stainless steel for improved resistance to helium embrittlement under HFIR irradiation

P.J. Maziasz, D.N. Braski

Journal:

Journal of Nuclear Materials

Year:

1984

Language:

english

File:

PDF, 2.52 MB

english, 1984

19

Swelling and swelling resistance possibilities of austenitic stainless steels in fusion reactors

Journal:

Journal of Nuclear Materials

Year:

1984

Language:

english

File:

PDF, 3.60 MB

english, 1984

20

A perspective on present and future alloy development efforts on austenitic stainless steels for fusion application

Journal:

Journal of Nuclear Materials

Year:

1985

Language:

english

File:

PDF, 867 KB

english, 1985

21

Modification of the grain boundary microstructure of the austenitic PCA stainless steel to improve helium embrittlement resistance

P.J. Maziasz, D.N. Braski

Journal:

Journal of Nuclear Materials

Year:

1986

Language:

english

File:

PDF, 621 KB

english, 1986

22

Postirradiation tensile behavior of nickel-doped ferritic steels

R.L. Klueh, P.J. Maziasz, J.M. Vitek

Journal:

Journal of Nuclear Materials

Year:

1986

Language:

english

File:

PDF, 735 KB

english, 1986

23

Temperature dependence of swelling in type 316 stainless steel irradiated in HFIR

S. Hamada, P.J. Maziasz, M.P. Tanaka, M. Suzuki, A. Hishinuma

Journal:

Journal of Nuclear Materials

Year:

1988

Language:

english

File:

PDF, 779 KB

english, 1988

24

Swelling behavior of austenitic stainless steels in a spectrally tailored reactor experiment: Implications for near-term fusion machines

R.E. Stoller, P.J. Maziasz, A.F. Rowcliffe, M.P. Tanaka

Journal:

Journal of Nuclear Materials

Year:

1988

Language:

english

File:

PDF, 728 KB

english, 1988

25

Formation and stability of radiation-induced phases in neutron-irradiated austenitic and ferritic steels

Journal:

Journal of Nuclear Materials

Year:

1989

Language:

english

File:

PDF, 2.44 MB

english, 1989

26

Void formation in 10Cr-2Mo ferritic steel irradiated in HFIR

M. Suzuki, A. Hishinuma, P.J. Maziasz, T. Sawai

Journal:

Journal of Nuclear Materials

Year:

1990

Language:

english

File:

PDF, 905 KB

english, 1990

27

Ultrafine defects inside precipitate particles produced in Type 316 stainless steel by irradiation in HFIR

S. Hamada, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1990

Language:

english

File:

PDF, 685 KB

english, 1990

28

Microstructural evolution in austenitic stainless steels irradiated to 57 dpa in HFIR

S. Hamada, M. Suzuki, P.J. Maziasz, A. Hishinuma

Journal:

Journal of Nuclear Materials

Year:

1991

Language:

english

File:

PDF, 350 KB

english, 1991

29

Impact behavior of reduced-activation ferritic steels irradiated in the Fast Flux Test Facility

R.L. Klueh, D.J. Alexander, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1992

Language:

english

File:

PDF, 1.38 MB

english, 1992

30

Microstructural evolution of austenitic stainless steels irradiated in spectrally tailored experiment in ORR at 400°C

T. Sawai, P.J. Maziasz, H. Kanazawa, A. Hishinuma

Journal:

Journal of Nuclear Materials

Year:

1992

Language:

english

File:

PDF, 384 KB

english, 1992

31

Modeling of strengthening mechanisms in irradiated fusion reactor first wall alloys

M.L. Grossbeck, P.J. Maziasz, A.F. Rowcliffe

Journal:

Journal of Nuclear Materials

Year:

1992

Language:

english

File:

PDF, 340 KB

english, 1992

32

Radiation-induced sensitization of a titanium-modified austenitic stainless steel irradiated in a spectral-tailored experiment at 60–400°C

T. Inazumi, G.E.C. Bell, P.J. Maziasz, T. Kondo

Journal:

Journal of Nuclear Materials

Year:

1992

Language:

english

File:

PDF, 378 KB

english, 1992

33

Compositional behavior and stability of MC-type precipitates in JPCA austenitic stainless steel during HFIR irradiation

M. Suzuki, S. Hamada, P.J. Maziasz, S. Jitsukawa, A. Hishinuma

Journal:

Journal of Nuclear Materials

Year:

1992

Language:

english

File:

PDF, 348 KB

english, 1992

34

Issues in replacing Cr–Mo steels and stainless steels with 9Cr–1Mo–V steel

R.W Swindeman, M.L Santella, P.J Maziasz, B.W Roberts, K Coleman

Journal:

International Journal of Pressure Vessels and Piping

Year:

2004

Language:

english

File:

PDF, 106 KB

english, 2004

35

Creep behavior of a new cast austenitic alloy

John P. Shingledecker, Philip J. Maziasz, Neal D. Evans, Michael J. Pollard

Journal:

International Journal of Pressure Vessels and Piping

Year:

2007

Language:

english

File:

PDF, 721 KB

english, 2007

36

Microstructural characterization of precipitates formed during high temperature testing and processing of iron-aluminide alloys

P.J Maziasz, C.G McKamey

Journal:

Materials Science and Engineering: A

Year:

1992

Language:

english

File:

PDF, 2.92 MB

english, 1992

37

The thermal stability of the microstructure of γ-based titanium aluminides

R.V. Ramanujan, P.J. Maziasz, C.T. Liu

Journal:

Acta Materialia

Year:

1996

Language:

english

File:

PDF, 2.83 MB

english, 1996

38

The development of alumina-forming austenitic stainless steels for high-temperature structural use

M. P. Brady, Y. Yamamoto, M. L. Santella, P. J. Maziasz, B. A. Pint, C. T. Liu, Z. P. Lu, H. Bei

Journal:

JOM Journal of the Minerals, Metals and Materials Society

Year:

2008

Language:

english

File:

PDF, 1.32 MB

english, 2008

39

The tensile properties of high oxide SAP containing helium and tritium

P.J. Maziasz, K. Farrell

Journal:

Journal of Nuclear Materials

Year:

1979

Language:

english

File:

PDF, 557 KB

english, 1979

40

Some effects of increased helium content on void formation and solute segregation in neutron irradiated type 316 stainless steel

Journal:

Journal of Nuclear Materials

Year:

1982

Language:

english

File:

PDF, 3.55 MB

english, 1982

41

Progress in alloy development in the fusion materials program

P.J. Maziasz, D.N. Braski, J.M. Vitek, F.W. Wiffen, R.L. Klueh, M.L. Grossbeck, E.E. Bloom

Journal:

Journal of Nuclear Materials

Year:

1982

Language:

english

File:

PDF, 276 KB

english, 1982

42

Preirradiation microstructural development designed to minimize properties degradation during irradiation in austenitic alloys

P.J. Maziasz, T.K. Roche

Journal:

Journal of Nuclear Materials

Year:

1981

Language:

english

File:

PDF, 540 KB

english, 1981

43

The influence of neutron irradiation at 55°C on the properties of austenitic stainless steels

F.W. Wiffen, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1981

Language:

english

File:

PDF, 612 KB

english, 1981

44

Tensile properties of unirradiated PCA from room temperature to 700°C

D.N. Braski, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1984

Language:

english

File:

PDF, 766 KB

english, 1984

45

Comparison of swelling and cavity microstructural development for type 316 stainless steel irradiated in EBR-II and HFIR

Journal:

Journal of Nuclear Materials

Year:

1984

Language:

english

File:

PDF, 889 KB

english, 1984

46

Helium effects on void formation in 9Cr-1MoVNb and 12Cr-1MoVW irradiated in HFIR

P.J. Maziasz, R.L. Klueh, J.M. Vitek

Journal:

Journal of Nuclear Materials

Year:

1986

Language:

english

File:

PDF, 1.61 MB

english, 1986

47

Control of helium effects in irradiated materials based on theory and experiment

L.K. Mansur, E.H. Lee, P.J. Maziasz, A.P. Rowcliffe

Journal:

Journal of Nuclear Materials

Year:

1986

Language:

english

File:

PDF, 1.97 MB

english, 1986

48

Microstructural development of austenitic stainless steels irradiated in HFIR

M.P. Tanaka, S. Hamada, A. Hishinuma, P.J. Maziasz

Journal:

Journal of Nuclear Materials

Year:

1988

Language:

english

File:

PDF, 764 KB

english, 1988

49

Microstructural development of 10Cr-2Mo ferritic steel irradiated to 57 dpa in HFIR

M. Suzuki, T. Sawai, P.J. Maziasz, A. Hishinuma

Journal:

Journal of Nuclear Materials

Year:

1991

Language:

english

File:

PDF, 990 KB

english, 1991

50

Microstructural evolution of welded austenitic stainless steels irradiated in the spectrally-tailored ORR experiment at 400°C

T. Sawai, P.J. Maziasz, A. Hishinuma

Journal:

Journal of Nuclear Materials

Year:

1991

Language:

english

File:

PDF, 1005 KB

english, 1991

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