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Digital Library / STP / STP1492-EB
Eighteen peer-reviewed papers focus on the irradiation embrittlement of reactor pressure vessel steels. This new publication provides a broad perspective on the development and application of trend curves used to predict fracture toughness transition temperatures in irradiated reactor pressure vessel steels. Papers cover materials ranging from erbium-tritide films to oxide dispersion strengthened (ODS) ferritic steels.
Table of Contents
Master Integrated Reactor Vessel Surveillance Program
Hall J., Spond D.
The Feasibility of Using a Risk-informed Approach for Calculating Reactor Pressure Vessel Heatup and Cooldown Operating Curves
Gamble R., Server W., Carter R.
Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels
Shtrombakh Y., Nikolaev Y.
Analysis of the Ductile-to-Brittle Transition Temperature Shift in a Commercial Power Plant With High Nickel Containing Weld Material
Efsing P., Jansson C., Mager T., Embring G.
Radiation Embrittlement of Cr-Ni-Mo and Cr-Mo RPV Steels
Nikolaev Y.
Attenuation of Neutron Radiation Damage Through a Simulated RPV Wall
Server W., Spanner J., Rosinski S., Brumovsky M., Kytka M.
Phosphorus Segregation and Intergranular Embrittlement in Thermally Aged and Neutron Irradiated Reactor Pressure Vessel Steels
Nishiyama Y., Onizawa K., Suzuki M.
Information Fusion Embrittlement Models for U.S. Power Reactor Pressure Vessel Steels
Wang J., Rao N., Konduri S.
Strain Hardening During Mechanical Twinning and Dislocation Channeling in Irradiated 316 Stainless Steels
Byun T., Hashimoto N.
Notch Strengthening and Its Impact on the Deformation and Fracture of 316L Stainless Steel
Wu X., Pan X., Stubbins J.
Irradiation Hardening and Microstructure Evolution of Ion-irradiated ODS Ferritic Steels
Yutani K., Kasada R., Kishimoto H., Kimura A.
Modelling of Radiation Damage in Fe-Cr Alloys
Malerba L., Terentyev D., Bonny G., Barashev A., Bjorkas C., Juslin N., Nordlund K., Domain C., Olsson P., Sandberg N., Wallenius J.
Kinetics of the Migration and Clustering of Extrinsic Gas in bcc Metals
Deo C., Srinivasan S., Baskes M., Maloy S., James M., Okuniewski M., Stubbins J.
Modeling the Interaction of Helium with Dislocations and Grain Boundaries in Alpha-Iron
Heinisch H., Gao F., Kurtz R.
DD Simulations of Dislocation-Crack Interaction During Fatigue
Mastorakos I., Zbib H.
Grain Growth in Nanocrystalline Metal Thin Films under In Situ Ion-Beam Irradiation
Kaoumi D., Motta A., Birtcher R.
Microstructural Features in Aged Erbium Tritide Films
Gelles D., Brewer L., Kotula P., Cowgill D., Busick C., Snow C.
Internal Probe to Detect Defects from Cascades—In-situ Ion Irradiation Experiments Revisited
Ishino S., Sekimura N., Abe H.
Author Index
Subject Index
Committee: E10
Paper ID: STP1492-EB
DOI: 10.1520/STP1492-EB
ISBN-EB: 978-0-8031-6826-8
 ASTM International is a member of CrossRef.
0-8031-3421-5
978-0-8031-3421-8
STP1492-EB
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