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Effects of radiation on nuclear materials and the nuclear fuel cycle : 24th volume

Author: Jeremy T Busby; Brady D Hanson; ASTM International.; ASTM International Committee E10 on Nuclear Technology and Applications.; ASTM Committee C-26 on Nuclear Fuel Cycle.
Publisher: West Conshohocken, PA : ASTM International, ©2010.
Series: Journal of ASTM International., Selected technical papers ;, STP 1513.
Edition/Format:   Print book : Conference publication : EnglishView all editions and formats
Summary:
"Fifteen peer-reviewed papers examine radiation damage for the entire fuel cycle. Topics cover: Surveillance programs around the world ; Detailed characterization of irradiated microstructures ; Radiation effects in oxide-dispersion strengthened alloys and austenitic stainless steels ; Modeling helium bubbles ; Finite-element modeling of fuel bundles."--Publisher's website.
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Genre/Form: Conference papers and proceedings
Congresses
Material Type: Conference publication
Document Type: Book
All Authors / Contributors: Jeremy T Busby; Brady D Hanson; ASTM International.; ASTM International Committee E10 on Nuclear Technology and Applications.; ASTM Committee C-26 on Nuclear Fuel Cycle.
ISBN: 9780803134256 0803134258
OCLC Number: 642231502
Notes: "ASTM stock #: STP 1513."
"This compilation of the Journal of ASTM International ... contains only the papers published in JAI that were presented at a symposium in Denver, CO from June 24-26, 2008 and sponsored by ASTM Committees E10 on Nuclear Technology and its Applications and C26 on the Nuclear Fuel Cycle"--Foreword.
Description: vii, 280 pages : illustrations ; 23 cm.
Contents: International atomic energy agency coordinated research projects on structural integrity of reactor pressure vessels / W.L. Server, R.K. Nanstad --
Analysis of the Belgian surveillance fracture toughness database using conventional and advanced master curve approaches / E. Lucon, M. Scibetta, R. Gérard --
Final results from the crack initiation and arrest of irradiated steel materials project on fracture mechanical assessments of pre-irradiated RPV steels used in German PWR / H. Hein, E. Keim, H. Schnabel, T. Seibert, A. Gundermann --
Embrittlement correlation method for the Japanese reactor pressure vessel materials / N. Soneda, K. Dohi, A. Nomoto, K. Nishida, S. Ishino --
Magnox steel reactor pressure vessel monitoring schemes-an overview / M.R. Wooton, R. Moskovic, C.J. Bolton, P.E.J. Flewitt --Investigation of beltline welding seam of the Greifswald WWER-440 unit 1 reactor pressure vessel / H.W. Viehrig, J. Schuhknecht, U. Rindelhardt, F.P. Weiss --
Microstructural characterization of RPV materials irradiated to high fluencies at high flux / N. Soneda, K. Dohi, K. Nishida, A. Nomoto, M. Tomimatsu, H. Matsuzawa --
Irradiation-induced grain-boundary solute segregation and its effect on ductile-to-brittle transition temperature in reactor pressure vessel steels / Y. Nishiyama, M. Yamaguchi, K. Onizawa, A. Iwase, H. Matsuzawa --
Irradiation-induced hardening and embrittlement of high-Cr ODS ferritic steels / H. Lee, R. Kasada, H.S. Cho, A. Kimura --
Kinetic monte carlo simulation of helium-bubble evolution in ODS steels --
A. Takahashi, S. Sharafat, K. Nagasawa, N. Ghoniem --
Study of microstructure and property changes in irradiated SS316 Wrapper of fast breeder test reactor / C.N. Venkiteswaran, V. Karthik, P. Parameswaran, N.G. Muralidharan, V.A. Raj, S. Saroja, V. Venugopal, M. Vijayalakshmi, K.V.K. Viswanathan, B. Raj --
Unusual enhancement of ductility observed during evolution of a "defomation wave" in 12Cr18Ni10Ti stainless steel irradiated in BN-350 / M.N. Gusev, O.P. Maksimkin, I.S. Osipov, N.S. Silniagina, F.A. Garner --
Interrelationship between true stress-true strain behavior and deformation microstructure in the plastic deformation of neutron-irradiated or work-hardened austenitic stainless steel / K. Kondo, Y. Miwa, T. Tsukada, S. Yamashita, K. Nishinoiri --
Influence of neutron irradiation on energy accumulation and dissipation during plastic flow and hardening of metallic polycrystals / D.A. Toktogulova, M.N. Gusev, O.P. Maksimkin, F.A. Garner --
Comparison of CANDU fuel bundle finite element model with unirradiated mechanical load experiments / T.J. Lampman, A. Popescu, J. Freire-Canosa.
Series Title: Journal of ASTM International., Selected technical papers ;, STP 1513.
Responsibility: JAI guest editors, Jeremy T. Busby, Brady D. Hanson.

Abstract:

"Fifteen peer-reviewed papers examine radiation damage for the entire fuel cycle. Topics cover: Surveillance programs around the world ; Detailed characterization of irradiated microstructures ; Radiation effects in oxide-dispersion strengthened alloys and austenitic stainless steels ; Modeling helium bubbles ; Finite-element modeling of fuel bundles."--Publisher's website.

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