High-temperature annealing of proton irradiated beryllium – A dilatometry-based study

Simos, Nikolaos; Elbakhshwan, Mohamed; Zhong, Zhong; Ghose, Sanjit; Savkliyildiz, Ilyas

doi:10.1016/j.jnucmat.2016.04.001

Title: High-temperature annealing of proton irradiated beryllium – A dilatometry-based study

Full Record
Other Related Research

Abstract

S—200 F grade beryllium has been irradiated with 160 MeV protons up to 1.2 10²⁰ cm^–2 peak fluence and irradiation temperatures in the range of 100–200 °C. To address the effect of proton irradiation on dimensional stability, an important parameter in its consideration in fusion reactor applications, and to simulate high temperature irradiation conditions, multi-stage annealing using high precision dilatometry to temperatures up to 740 °C were conducted in air. X-ray diffraction studies were also performed to compliment the macroscopic thermal study and offer a microscopic view of the irradiation effects on the crystal lattice. The primary objective was to qualify the competing dimensional change processes occurring at elevated temperatures namely manufacturing defect annealing, lattice parameter recovery, transmutation ⁴He and ³H diffusion and swelling and oxidation kinetics. Further, quantification of the effect of irradiation dose and annealing temperature and duration on dimensional changes is sought. Here, the study revealed the presence of manufacturing porosity in the beryllium grade, the oxidation acceleration effect of irradiation including the discontinuous character of oxidation advancement, the effect of annealing duration on the recovery of lattice parameters recovery and the triggering temperature for transmutation gas diffusion leading to swelling.

Authors:

Simos, Nikolaos ^[1]; Elbakhshwan, Mohamed ^[1]; Zhong, Zhong ^[1]; Ghose, Sanjit ^[1]; Savkliyildiz, Ilyas ^[2]

Brookhaven National Lab. (BNL), Upton, NY (United States)
Rutgers Univ., New Brunswick, NJ (United States)

Publication Date:: Thu Apr 07 00:00:00 EDT 2016

Research Org.:: Brookhaven National Lab. (BNL), Upton, NY (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Nuclear Physics (NP)

OSTI Identifier:: 1337618

Report Number(s):: BNL-112575-2016-JA
Journal ID: ISSN 0022-3115; R&D Project: 19432; NT010400

Grant/Contract Number:: SC00112704

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 477; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; irradiation damage; high temperature annealing; oxidation; transmutation gas; beryllium

Citation Formats


                    Simos, Nikolaos, Elbakhshwan, Mohamed, Zhong, Zhong, Ghose, Sanjit, and Savkliyildiz, Ilyas. High-temperature annealing of proton irradiated beryllium – A dilatometry-based study.  United States: N. p., 2016. 
Web.  doi:10.1016/j.jnucmat.2016.04.001.

Copy to clipboard


                    Simos, Nikolaos, Elbakhshwan, Mohamed, Zhong, Zhong, Ghose, Sanjit, & Savkliyildiz, Ilyas. High-temperature annealing of proton irradiated beryllium – A dilatometry-based study.  United States.  https://doi.org/10.1016/j.jnucmat.2016.04.001

Copy to clipboard


                    Simos, Nikolaos, Elbakhshwan, Mohamed, Zhong, Zhong, Ghose, Sanjit, and Savkliyildiz, Ilyas. Thu .  
"High-temperature annealing of proton irradiated beryllium – A dilatometry-based study".  United States.  https://doi.org/10.1016/j.jnucmat.2016.04.001.  https://www.osti.gov/servlets/purl/1337618.

Copy to clipboard


                    
@article{osti_1337618,

  title        = {High-temperature annealing of proton irradiated beryllium – A dilatometry-based study},

  author       = {Simos, Nikolaos and Elbakhshwan, Mohamed and Zhong, Zhong and Ghose, Sanjit and Savkliyildiz, Ilyas},

  abstractNote = {S—200 F grade beryllium has been irradiated with 160 MeV protons up to 1.2 1020 cm–2 peak fluence and irradiation temperatures in the range of 100–200 °C. To address the effect of proton irradiation on dimensional stability, an important parameter in its consideration in fusion reactor applications, and to simulate high temperature irradiation conditions, multi-stage annealing using high precision dilatometry to temperatures up to 740 °C were conducted in air. X-ray diffraction studies were also performed to compliment the macroscopic thermal study and offer a microscopic view of the irradiation effects on the crystal lattice. The primary objective was to qualify the competing dimensional change processes occurring at elevated temperatures namely manufacturing defect annealing, lattice parameter recovery, transmutation 4He and 3H diffusion and swelling and oxidation kinetics. Further, quantification of the effect of irradiation dose and annealing temperature and duration on dimensional changes is sought. Here, the study revealed the presence of manufacturing porosity in the beryllium grade, the oxidation acceleration effect of irradiation including the discontinuous character of oxidation advancement, the effect of annealing duration on the recovery of lattice parameters recovery and the triggering temperature for transmutation gas diffusion leading to swelling.},

  doi          = {10.1016/j.jnucmat.2016.04.001},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 477,

  place        = {United States},

  year         = {Thu Apr 07 00:00:00 EDT 2016},

  month        = {Thu Apr 07 00:00:00 EDT 2016}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.jnucmat.2016.04.001

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 4 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Long Baseline Neutrino Experiment (LBNE) Target Material Radiation Damage from Energetic Protons of the Brookhaven Linear Isotope Production (BLIP) Facility

Technical Report Simos, Nikolaos

In search of a low-Z pion production target for the Long Baseline Neutrino Facility (LBNF) of the Deep Underground Neutrino Experiment (DUNE) various grades of graphite were irradiated with 140-180 MeV protons to fluence up to ~6 10²⁰ cm^-2 and irradiation temperatures in the range of 100-200oC. The objective of the irradiation experiment was to assess the radiation induced changes in the graphite onset by its interaction with energetic protons and deduce some measure of performance and survivability under the design conditions of LBNF. A multi-faceted post-irradiation evaluation was conducted to both qualify and quantify the induced material property changes.more »« less
https://doi.org/10.2172/1473632

Full Text Available
Proton irradiation effects on beryllium – A macroscopic assessment

Journal Article Simos, Nikolaos ; Elbakhshwan, Mohamed ; Zhong, Zhong ; ... - Journal of Nuclear Materials

Beryllium, due to its excellent neutron multiplication and moderation properties, in conjunction with its good thermal properties, is under consideration for use as plasma facing material in fusion reactors and as a very effective neutron reflector in fission reactors. While it is characterized by unique combination of structural, chemical, atomic number, and neutron absorption cross section it suffers, however, from irradiation generated transmutation gases such as helium and tritium which exhibit low solubility leading to supersaturation of the Be matrix and tend to precipitate into bubbles that coalesce and induce swelling and embrittlement thus degrading the metal and limiting itsmore »« less
Cited by 2
https://doi.org/10.1016/j.jnucmat.2016.06.048

Full Text Available
Helium induced swelling and tritium trapping mechanisms in irradiated beryllium: A comprehensive approach

Conference Scaffidi-Argentina, F ; Dalle Donne, M ; Ferrero, C

Since beryllium is considered as one of the best neutron multipliers for the blanket of a fusion reactor, several studies have been initiated to evaluate this material behavior under irradiation both for typical operating and accidental conditions. The most important effects of radiation damage in beryllium are swelling, embrittlement and tritium retention. The helium produced mainly by the reaction {sup 9}Be(n,2n)2 {sup 4}He is the dominant cause of beryllium swelling which represents the major lifetime limiting factor for the material. Furthermore, the tritium inventory in beryllium, produced by simultaneous transmutation reactions, constitutes a safety hazard in case of accidental temperaturemore »« less
Investigations of radiation resistant beryllium grades for nuclear fusion applications

Book Kupriyanov, I B ; Gorokhov, V A ; Nikolaev, G N ; ...

R and D results on beryllium with high radiation resistance obtained recently are described in this report. The data are presented on nine different grades of isotropic beryllium manufactured by VNIINM and distinguished by both initial powder characteristics and properties of billets, made of these powders. The average grain size of the investigated beryllium grades varied from 8 to 26 {micro}m, the content of beryllium oxide was 0.9--3.9 wt.%, the dispersity of beryllium oxide 0.04--0.5 {micro}m, tensile strength 250--650 MPa. All materials were irradiated in SM-2 reactor over the temperature range 550--780 C. The results of the investigation showed, thatmore »« less
Development of radiation resistant grades of beryllium for nuclear and fusion facilities

Conference Kupriyanov, I B ; Gorokhov, V A ; Nikolaev, G N

R&D results on beryllium with high radiation resistance obtained recently are described in this report. The data are presented on nine different grades of isotropic beryllium manufactured by VNIINM and distinguished by both initial powder characteristics and properties of billets, made of these powders. The average grain size of the investigated beryllium grades varied from 8 to 26 {mu}m, the content of beryllium oxide was 0.9 - 3.9 wt.%, the dispersity of beryllium oxide - 0.04 - 0.5 {mu}m, tensile strength -- 250 - 650 MPa. All materials were irradiated in SM - 2 reactor over the temperature range 550more »« less
Full Text Available

Similar Records