Studies of low temperature, low flux radiation embrittlement of nuclear reactor structural materials. Final report

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A large matrix of simple alloys and complex commercial type steels was irradiated over a range of fluxes at 60 C up to a fast fluence of about 3 {times} 10{sup 22} n/m{sup 2}. Combined with data in the literature, these results show a negligible effect of flux on irradiation hardening in the range of 2 {times} 10{sup 13} to 5 {times} 10{sup 18} n/m{sup 2}-s. This observation lends indirect support to the proposal that the accelerated embrittlement in the High Flux Isotope Reactor surveillance steels was due to an anomalously high level of damage from gamma rays. A weak ... continued below

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28 p.

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Odette, G.R. & Lucas, G.E. September 2, 1998.

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Description

A large matrix of simple alloys and complex commercial type steels was irradiated over a range of fluxes at 60 C up to a fast fluence of about 3 {times} 10{sup 22} n/m{sup 2}. Combined with data in the literature, these results show a negligible effect of flux on irradiation hardening in the range of 2 {times} 10{sup 13} to 5 {times} 10{sup 18} n/m{sup 2}-s. This observation lends indirect support to the proposal that the accelerated embrittlement in the High Flux Isotope Reactor surveillance steels was due to an anomalously high level of damage from gamma rays. A weak dependence of hardening on a number of elements, including copper, nickel, phosphorus, molybdenum and manganese, can be described by a simple empirical chemistry factor. Particular combinations of elements resulted in hardening differences of up to about 60% in the complex commercial type steels and up to about 100% in simple model alloys. Direct effects of microstructure appear to be minimal. Hardening varies with the square root of fluence above a threshold around 4 {times} 10{sup 20} n/m{sup 2}. The results suggest that low temperature hardening is dominated by local intracascade processes leading to the formation of small defect-solute clusters/complexes. The observed hardening corresponds to nominal maximum end-of-life transition temperature shifts in support structure steels of about 120 C.

Physical Description

28 p.

Notes

INIS; OSTI as DE99000070

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  • Other Information: PBD: 2 Sep 1998

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  • Other: DE99000070
  • Report No.: DOE/ER/75902--T1
  • Grant Number: FG03-93ER75902
  • DOI: 10.2172/665938 | External Link
  • Office of Scientific & Technical Information Report Number: 665938
  • Archival Resource Key: ark:/67531/metadc709770

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  • September 2, 1998

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  • Sept. 12, 2015, 6:31 a.m.

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  • Nov. 5, 2015, 4:03 p.m.

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Odette, G.R. & Lucas, G.E. Studies of low temperature, low flux radiation embrittlement of nuclear reactor structural materials. Final report, report, September 2, 1998; United States. (digital.library.unt.edu/ark:/67531/metadc709770/: accessed August 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.