Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor

N. O. Cetiner; J. R. Burns; A. G. Le Coq; K. D. Linton; C. M. Petrie; J. N. Stevens; B. Winterholer; G. Raveu

Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor

N. O. Cetiner, J. R. Burns, A. G. Le Coq, K. D. Linton, C. M. Petrie, J. N. Stevens, B. Winterholer, G. Raveu

Research output: Contribution to conference › Paper › peer-review

Abstract

Commercial nuclear reactors use neutron absorbers (material being mainly Ag-In-Cd and B₄C) to control power level and to safely shut down the plant. Recently, there has been increased interest in accident-tolerant absorber materials that can survive the extreme conditions during a beyond-design-basis accident for an extended period of time. Framatome developed four new absorber materials that are more stable under severe accident conditions and have higher melting points compared with current absorbers. Oak Ridge National Laboratory is supporting this ongoing research and development by designing an irradiation experiment to test these unique absorber materials to gain an understanding of the irradiation effects under realistic light-water-reactor temperatures and temperature gradients and verify their performance under these environmental conditions. This project is funded by the US Department of Energy, Office of Nuclear Energy Nuclear Science User Facility. Ultimately, the data generated from this research will assist in quantifying the irradiation-induced swelling of different absorber materials needed to predict and demonstrate performance under irradiation.

Original language	English
Pages	996-1002
Number of pages	7
State	Published - 2020
Event	14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States Duration: Sep 22 2019 → Sep 27 2019

Conference

Conference	14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
Country/Territory	United States
City	Seattle
Period	09/22/19 → 09/27/19

Funding

This project is funded by the US Department of Energy, Office of Nuclear Energy Nuclear Science User Facility. Ultimately, the data generated from this research will assist in quantifying the irradiation-induced swelling of different absorber materials needed to predict and demonstrate performance under irradiation. ∗ This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-

Cite this

Cetiner, N. O., Burns, J. R., Le Coq, A. G., Linton, K. D., Petrie, C. M., Stevens, J. N., Winterholer, B., & Raveu, G. (2020). Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor. 996-1002. Paper presented at 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Seattle, United States.

@conference{735c6d0b997c409288a10f8b7de02e81,

title = "Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor",

abstract = "Commercial nuclear reactors use neutron absorbers (material being mainly Ag-In-Cd and B4C) to control power level and to safely shut down the plant. Recently, there has been increased interest in accident-tolerant absorber materials that can survive the extreme conditions during a beyond-design-basis accident for an extended period of time. Framatome developed four new absorber materials that are more stable under severe accident conditions and have higher melting points compared with current absorbers. Oak Ridge National Laboratory is supporting this ongoing research and development by designing an irradiation experiment to test these unique absorber materials to gain an understanding of the irradiation effects under realistic light-water-reactor temperatures and temperature gradients and verify their performance under these environmental conditions. This project is funded by the US Department of Energy, Office of Nuclear Energy Nuclear Science User Facility. Ultimately, the data generated from this research will assist in quantifying the irradiation-induced swelling of different absorber materials needed to predict and demonstrate performance under irradiation.",

author = "Cetiner, {N. O.} and Burns, {J. R.} and {Le Coq}, {A. G.} and Linton, {K. D.} and Petrie, {C. M.} and Stevens, {J. N.} and B. Winterholer and G. Raveu",

note = "Publisher Copyright: Copyright {\textcopyright} GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference.All rights reserved.; 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 ; Conference date: 22-09-2019 Through 27-09-2019",

year = "2020",

language = "English",

pages = "996--1002",

}

Cetiner, NO, Burns, JR, Le Coq, AG, Linton, KD , Petrie, CM, Stevens, JN, Winterholer, B & Raveu, G 2020, 'Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor', Paper presented at 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Seattle, United States, 09/22/19 - 09/27/19 pp. 996-1002.

Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor. / Cetiner, N. O.; Burns, J. R.; Le Coq, A. G. et al.
2020. 996-1002 Paper presented at 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Seattle, United States.

Research output: Contribution to conference › Paper › peer-review

TY - CONF

T1 - Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor

AU - Cetiner, N. O.

AU - Burns, J. R.

AU - Le Coq, A. G.

AU - Linton, K. D.

AU - Petrie, C. M.

AU - Stevens, J. N.

AU - Winterholer, B.

AU - Raveu, G.

PY - 2020

Y1 - 2020

N2 - Commercial nuclear reactors use neutron absorbers (material being mainly Ag-In-Cd and B4C) to control power level and to safely shut down the plant. Recently, there has been increased interest in accident-tolerant absorber materials that can survive the extreme conditions during a beyond-design-basis accident for an extended period of time. Framatome developed four new absorber materials that are more stable under severe accident conditions and have higher melting points compared with current absorbers. Oak Ridge National Laboratory is supporting this ongoing research and development by designing an irradiation experiment to test these unique absorber materials to gain an understanding of the irradiation effects under realistic light-water-reactor temperatures and temperature gradients and verify their performance under these environmental conditions. This project is funded by the US Department of Energy, Office of Nuclear Energy Nuclear Science User Facility. Ultimately, the data generated from this research will assist in quantifying the irradiation-induced swelling of different absorber materials needed to predict and demonstrate performance under irradiation.

AB - Commercial nuclear reactors use neutron absorbers (material being mainly Ag-In-Cd and B4C) to control power level and to safely shut down the plant. Recently, there has been increased interest in accident-tolerant absorber materials that can survive the extreme conditions during a beyond-design-basis accident for an extended period of time. Framatome developed four new absorber materials that are more stable under severe accident conditions and have higher melting points compared with current absorbers. Oak Ridge National Laboratory is supporting this ongoing research and development by designing an irradiation experiment to test these unique absorber materials to gain an understanding of the irradiation effects under realistic light-water-reactor temperatures and temperature gradients and verify their performance under these environmental conditions. This project is funded by the US Department of Energy, Office of Nuclear Energy Nuclear Science User Facility. Ultimately, the data generated from this research will assist in quantifying the irradiation-induced swelling of different absorber materials needed to predict and demonstrate performance under irradiation.

UR - http://www.scopus.com/inward/record.url?scp=85081082958&partnerID=8YFLogxK

M3 - Paper

AN - SCOPUS:85081082958

SP - 996

EP - 1002

T2 - 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019

Y2 - 22 September 2019 through 27 September 2019

ER -

Cetiner NO, Burns JR, Le Coq AG, Linton KD , Petrie CM, Stevens JN et al.. Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor. 2020. Paper presented at 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019, Seattle, United States.

Thermal and neutronic analysis for irradiation of advanced neutron-absorbing material in the high flux isotope reactor

Abstract

Conference

Funding

Other files and links

Fingerprint

Cite this