Swelling of type-316 stainless steel at high fluences in EBR-II

Kenfield, T.A.; Appleby, W.K.; Busboom, H.J.; Bell, William L.

doi:10.1016/0022-3115(78)90031-4

Cited by 21 publications

(5 citation statements)

References 6 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Next, we examine the quan titative data at ~400 to 700°C. 222 Barton et al, 39 and LeNaour et al 116 The swelling data of Bramman et al 113 and several microstructural data points by Lee et al 223 are also included. Figure 10(a) shows that voids get larger as Irradiation temperature or as fluence Increases.…”

Section: B Voidsmentioning

confidence: 99%

Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Maziasz¹

1985

View full text Add to dashboard Cite

A major purpose of the Techni cal Information Center is to provide the broadest dissemination possi ble of information contained in DOE's Research and Development Reports to business, industry, the academib community, and federal, state and local governments.Although a small portion of this report is not reproducible, it is being made available to expedite the availability of information on the research discussed herein.

show abstract

Section: B Voidsmentioning

confidence: 99%

Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Maziasz¹

1985

View full text Add to dashboard Cite

show abstract

“…Relative to observations on many other heats of SA 315 irradiated in EBR-II [9,10,[31][32][33][34][35], this 00 heat has far fewer total voids, but a larger fraction of precipitate associated voids. The other heats of steel have, in general, many more loops and higher dislocation concentrations.…”

Section: Ebr-ii Irradiationsmentioning

confidence: 65%

Void-Precipitate Association During Neutron Irradiation of Austenitic Stainless Steel

Pedraza

Maziasz

1987

Radiation-Induced Changes in Microstructure: 13th International Symposium (Part I)

View full text Add to dashboard Cite

Microstructural data has recently become available on a single heat of 316 stainless steel irradiated in EBR-II and HFIR, over a wide range of irradiation temperature (55 to 750 C), dose (7 to 75 dpa), and helium generation rate (0.5 to 55 at. ppm He/dpa). dislocation and bubble evolution. Analysis of this data suggests a mechanism which relates to the origin and subsequent growth of precipitate associated voids.

show abstract

“…The irradiation was performed at 823 K and up to 6 dpa with a damage rate of 1 Â 10 À3 dpa/s. Kenfield et al indicated that there is a good correlation between the electron and neutron irradiation void swelling results at temperatures above 723 K [21]. Makin et al also confirmed that both of these swelling rates agreed within a factor of two over the temperature range 723-843 K without any temperature shifts or correction factors [22].…”

Section: Methodsmentioning

confidence: 72%

Grain boundary engineering of austenitic steel PNC316 for use in nuclear reactors

Sekine¹,

Sakaguchi²,

Endo³

et al. 2011

Journal of Nuclear Materials

View full text Add to dashboard Cite

Austenitic stainless steel PNC316 was subjected to grain boundary engineering (GBE). It was found that the grain boundary engineered PNC316 (PNC316-GBEM) had a coincidence site lattice (CSL) fraction of 86% and that the network of random grain boundaries was perfectly divided by the CSL boundaries. The thermal stability and the void swelling behavior of PNC316-GBEM were investigated by means of SEM and TEM analyses. After thermal aging at 973 K for 100 h, structural changes were observed neither in the grain boundary networks of PNC316-GBEM nor in another sample of PNC316-GBEM subjected to 20% additional cold rolling, PNC316-GBEM20%CW. PNC316-GBEM showed a higher void swelling rate than as-received PNC316 (PNC316-AS). However, with additional 20% cold rolling after GBE, the void swelling rate decreased to as low as that of PNC316-AS

show abstract

Swelling of type-316 stainless steel at high fluences in EBR-II

Cited by 21 publications

References 6 publications

Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Effects of helium content of microstructural development in Type 316 stainless steel under neutron irradiation

Void-Precipitate Association During Neutron Irradiation of Austenitic Stainless Steel

Grain boundary engineering of austenitic steel PNC316 for use in nuclear reactors

Contact Info

Product

Resources

About