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Title: IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC-MARTENSITIC STEELS IRRADIATED IN THE BN-350 FAST REACTOR

Abstract

Russian ferritic/martensitic steels EP-450 and EP-823 were irradiated to 20-60 dpa in the BN-350 fast reactor in the form of pressurized creep tubes and small rings used for mechanical property tests. Data derived from these steels serves to enhance our understanding of the general behavior of this class of steels. It appears that these steels exhibit behavior that is very consistent with that of Western steels. Swelling is relatively low at high neutron exposure and confined to temperatures less then 420 degrees C, but may be camouflaged somewhat by precipitation-related densification. The irradiation creep studies confirm that the creep compliance of F/M steels is about one-half that of austenitic steels, and that the loss of strength at test temperatures above 500 degrees C is a problem generic to all F/M steels. This conclusion is supported by post-irradiation measurement of short-term mechanical properties. At temperatures below 500 degrees C both steels retain their high strength (yield stress 0.2=550-600 MPa), but at higher test temperatures a sharp decrease of strength properties occurs. However, the irradiated steels still retain high post-irradiation ductility at test temperatures in the range of 20-700 degrees C.

Authors:
; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
902071
Report Number(s):
PNNL-SA-31905
AT6020100; TRN: US0702758
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Book
Resource Relation:
Related Information: Fusion Materials: Semi-Annual Progress Report Ending December 31, 2001, 31:106-114
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; AUSTENITIC STEELS; COMPLIANCE; CREEP; DUCTILITY; FAST REACTORS; IRRADIATION; MECHANICAL PROPERTIES; NEUTRONS; STEELS; SWELLING

Citation Formats

Porollo, S I, Konobeev, Yu V, Dvoriashin, A M, Budylkin, N I, Mironova, E G, Leontyeva-Smirnova, M V, Loltukhovsky, A G, Bochvar, A A, and Garner, Francis A. IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC-MARTENSITIC STEELS IRRADIATED IN THE BN-350 FAST REACTOR. United States: N. p., 2002. Web.
Porollo, S I, Konobeev, Yu V, Dvoriashin, A M, Budylkin, N I, Mironova, E G, Leontyeva-Smirnova, M V, Loltukhovsky, A G, Bochvar, A A, & Garner, Francis A. IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC-MARTENSITIC STEELS IRRADIATED IN THE BN-350 FAST REACTOR. United States.
Porollo, S I, Konobeev, Yu V, Dvoriashin, A M, Budylkin, N I, Mironova, E G, Leontyeva-Smirnova, M V, Loltukhovsky, A G, Bochvar, A A, and Garner, Francis A. Sun . "IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC-MARTENSITIC STEELS IRRADIATED IN THE BN-350 FAST REACTOR". United States. https://www.osti.gov/servlets/purl/902071.
@article{osti_902071,
title = {IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC-MARTENSITIC STEELS IRRADIATED IN THE BN-350 FAST REACTOR},
author = {Porollo, S I and Konobeev, Yu V and Dvoriashin, A M and Budylkin, N I and Mironova, E G and Leontyeva-Smirnova, M V and Loltukhovsky, A G and Bochvar, A A and Garner, Francis A},
abstractNote = {Russian ferritic/martensitic steels EP-450 and EP-823 were irradiated to 20-60 dpa in the BN-350 fast reactor in the form of pressurized creep tubes and small rings used for mechanical property tests. Data derived from these steels serves to enhance our understanding of the general behavior of this class of steels. It appears that these steels exhibit behavior that is very consistent with that of Western steels. Swelling is relatively low at high neutron exposure and confined to temperatures less then 420 degrees C, but may be camouflaged somewhat by precipitation-related densification. The irradiation creep studies confirm that the creep compliance of F/M steels is about one-half that of austenitic steels, and that the loss of strength at test temperatures above 500 degrees C is a problem generic to all F/M steels. This conclusion is supported by post-irradiation measurement of short-term mechanical properties. At temperatures below 500 degrees C both steels retain their high strength (yield stress 0.2=550-600 MPa), but at higher test temperatures a sharp decrease of strength properties occurs. However, the irradiated steels still retain high post-irradiation ductility at test temperatures in the range of 20-700 degrees C.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2002},
month = {9}
}

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