Irradiation Effects in Structural Alloys for Thermal and Fast Reactors
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Published By ASTM International

9780803161900

Latest Documents Most Cited Documents Contributed Authors Related Sources Related Keywords

High-Temperature Embrittlement of AISI Type 316 Austenitic Stainless Steels after Irradiation

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41857s ◽

2009 ◽

pp. 352-352-19 ◽

Cited By ~ 1

Author(s):

M. Weisz ◽

J. Malkin ◽

J. Erler ◽

J. P. Andre

Keyword(s):

High Temperature ◽

Stainless Steels ◽

Austenitic Stainless Steels ◽

Aisi Type

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Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41850s ◽

2009 ◽

pp. 242-242-19 ◽

Cited By ~ 2

Author(s):

M. S. Wechsler ◽

R. G. Berggreen ◽

N. E. Hinkle ◽

W. J. Stelzman

Keyword(s):

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Radiation Hardening ◽

Pressure Vessel Steel ◽

Vessel Steel ◽

Reactor Pressure Vessel Steel ◽

Reactor Pressure

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Effects of Interstitial Elements on Radiation Hardening in Mild Steels

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41849s ◽

2009 ◽

pp. 215-215-27 ◽

Cited By ~ 6

Author(s):

E. A. Little ◽

D. R. Harries

Keyword(s):

Radiation Hardening ◽

Interstitial Elements

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Comparison of Radiation Damage Studies and Fuel Cladding Performance for lncoloy-800

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41860s ◽

2009 ◽

pp. 400-400-14 ◽

Cited By ~ 1

Author(s):

F. A. Comprelli ◽

H. J. Busboom ◽

C. N. Spalaris

Keyword(s):

Radiation Damage ◽

Fuel Cladding

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Neutron Dosimetry for Fast-Reactor Irradiation and Surveillance Testing

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41856s ◽

2009 ◽

pp. 342-342-10

Author(s):

H. H. Yoshikawa ◽

W. N. McElroy

Keyword(s):

Fast Reactor ◽

Reactor Irradiation ◽

Neutron Dosimetry

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Effect of Irradiation on Mechanical Properties of Cobalt-Base Alloys

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41855s ◽

2009 ◽

pp. 336-336-6

Author(s):

J. G. Y. Chow

Keyword(s):

Mechanical Properties ◽

Cobalt Base

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Notch Ductility, Tensile and Neutron Spectrum Analyses of PM-2A Reactor Pressure Vessel

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41846s ◽

2009 ◽

pp. 135-135-21

Author(s):

C. Z. Serpan ◽

H. E. Watson

Keyword(s):

Neutron Spectrum ◽

Pressure Vessel ◽

Reactor Pressure Vessel ◽

Reactor Pressure

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The Effect of Cold Work, Thermal Treatment, and Neutron Irradiation on the Fracture Toughness of Zircaloy-2

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41840s ◽

2009 ◽

pp. 3-3-14

Author(s):

R. G. Rowe ◽

R. G. Hoagland

Keyword(s):

Fracture Toughness ◽

Thermal Treatment ◽

Neutron Irradiation ◽

Cold Work

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Introduction

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41839s ◽

2009 ◽

pp. 1-1-2

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Postirradiation Tensile Behavior of 300 Series Stainless Steels

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors ◽

10.1520/stp41858s ◽

2009 ◽

pp. 371-371-19 ◽

Cited By ~ 1

Author(s):

J. J. Holmes ◽

R. E. Robbins ◽

A. J. Lovell

Keyword(s):

Stainless Steels ◽

Tensile Behavior

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Irradiation Effects in Structural Alloys for Thermal and Fast ReactorsLatest Publications

TOTAL DOCUMENTS

H-INDEX

Published By ASTM International

High-Temperature Embrittlement of AISI Type 316 Austenitic Stainless Steels after Irradiation

Radiation Hardening and Embrittlement in a Reactor Pressure Vessel Steel

Effects of Interstitial Elements on Radiation Hardening in Mild Steels

Comparison of Radiation Damage Studies and Fuel Cladding Performance for lncoloy-800

Neutron Dosimetry for Fast-Reactor Irradiation and Surveillance Testing

Effect of Irradiation on Mechanical Properties of Cobalt-Base Alloys

Notch Ductility, Tensile and Neutron Spectrum Analyses of PM-2A Reactor Pressure Vessel

The Effect of Cold Work, Thermal Treatment, and Neutron Irradiation on the Fracture Toughness of Zircaloy-2

Introduction

Postirradiation Tensile Behavior of 300 Series Stainless Steels

Irradiation Effects in Structural Alloys for Thermal and Fast Reactors
Latest Publications