Coverart for item
The Resource Effects of radiation on nuclear materials and the nuclear fuel cycle : 24th volume, JAI guest editors, Jeremy T. Busby, Brady D. Hanson

Effects of radiation on nuclear materials and the nuclear fuel cycle : 24th volume, JAI guest editors, Jeremy T. Busby, Brady D. Hanson

Label
Effects of radiation on nuclear materials and the nuclear fuel cycle : 24th volume
Title
Effects of radiation on nuclear materials and the nuclear fuel cycle
Title remainder
24th volume
Statement of responsibility
JAI guest editors, Jeremy T. Busby, Brady D. Hanson
Contributor
Subject
Genre
Language
eng
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
Member of
Cataloging source
UPM
Illustrations
illustrations
Index
index present
LC call number
  • T1
  • TK9185.A1
LC item number
  • .A5 no.1513
  • E445 2010
Literary form
non fiction
Nature of contents
bibliography
http://library.link/vocab/relatedWorkOrContributorDate
1972-
http://library.link/vocab/relatedWorkOrContributorName
  • Busby, Jeremy T.
  • Hanson, Brady D.
  • ASTM International
  • ASTM International Committee E10 on Nuclear Technology and Applications
  • ASTM Committee C-26 on Nuclear Fuel Cycle
Series statement
Journal of ASTM International, selected technical papers
Series volume
STP 1513
http://library.link/vocab/subjectName
  • Nuclear reactors
  • Nuclear fuels
Label
Effects of radiation on nuclear materials and the nuclear fuel cycle : 24th volume, JAI guest editors, Jeremy T. Busby, Brady D. Hanson
Instantiates
Publication
Note
  • "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
Bibliography note
Includes bibliographical references and indexes
Carrier category
volume
Carrier category code
  • nc
Carrier MARC source
rdacarrier
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
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
Control code
642231502
Dimensions
23 cm
Extent
vii, 280 pages
Isbn
9780803134256
Media category
unmediated
Media MARC source
rdamedia
Media type code
  • n
Other physical details
illustrations
System control number
(OCoLC)642231502
Label
Effects of radiation on nuclear materials and the nuclear fuel cycle : 24th volume, JAI guest editors, Jeremy T. Busby, Brady D. Hanson
Publication
Note
  • "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
Bibliography note
Includes bibliographical references and indexes
Carrier category
volume
Carrier category code
  • nc
Carrier MARC source
rdacarrier
Content category
text
Content type code
  • txt
Content type MARC source
rdacontent
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
Control code
642231502
Dimensions
23 cm
Extent
vii, 280 pages
Isbn
9780803134256
Media category
unmediated
Media MARC source
rdamedia
Media type code
  • n
Other physical details
illustrations
System control number
(OCoLC)642231502

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