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Title: Measurement of effective Sr diffusion coefficients in IG-110 graphite

Authors:
ORCiD logo; ; ; ORCiD logo
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
1787922
Grant/Contract Number:  
NE000118 Mod 007; NEUP-12830
Resource Type:
Publisher's Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Name: Journal of Nuclear Materials Journal Volume: 555 Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Weilert, T. M., Walton, K. L., Loyalka, S. K., and Brockman, J. D. Measurement of effective Sr diffusion coefficients in IG-110 graphite. Netherlands: N. p., 2021. Web. doi:10.1016/j.jnucmat.2021.153102.
Weilert, T. M., Walton, K. L., Loyalka, S. K., & Brockman, J. D. Measurement of effective Sr diffusion coefficients in IG-110 graphite. Netherlands. https://doi.org/10.1016/j.jnucmat.2021.153102
Weilert, T. M., Walton, K. L., Loyalka, S. K., and Brockman, J. D. Mon . "Measurement of effective Sr diffusion coefficients in IG-110 graphite". Netherlands. https://doi.org/10.1016/j.jnucmat.2021.153102.
@article{osti_1787922,
title = {Measurement of effective Sr diffusion coefficients in IG-110 graphite},
author = {Weilert, T. M. and Walton, K. L. and Loyalka, S. K. and Brockman, J. D.},
abstractNote = {},
doi = {10.1016/j.jnucmat.2021.153102},
journal = {Journal of Nuclear Materials},
number = C,
volume = 555,
place = {Netherlands},
year = {Mon Nov 01 00:00:00 EDT 2021},
month = {Mon Nov 01 00:00:00 EDT 2021}
}

Works referenced in this record:

Laboratory determinations of strontium diffusion coefficients in graphite
journal, November 1976


ICP-MS measurement of iodine diffusion in IG-110 graphite for HTGR/VHTR
journal, May 2016


In-pile release behavior of metallic fission products in graphite materials of an htgr fuel assembly
journal, June 1987


High-Temperature Reactor Fuel Fission Product Release and Distribution at 1600 to 1800°C
journal, December 1991

  • Schenk, Werner; Nabielek, Heinz
  • Nuclear Technology, Vol. 96, Issue 3
  • DOI: 10.13182/NT96-3-323

ICP-MS measurement of diffusion coefficients of Cs in NBG-18 graphite
journal, November 2015


Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test
journal, April 2018


The diffusion of Sr in the graphitic Matrix A3-3 in vacuum and in the presence of hydrogen
journal, September 1991


Distribution of fission products in irradiated graphite materials of HTGR fuel assemblies: Third and fourth OGL-1 fuels
journal, November 1985


Measurement of cesium diffusion coefficients in graphite IG-110
journal, May 2015


Calibration of a system for measurements of diffusion coefficients of fission products in HTGR/VHTR core materials
journal, December 2015

  • Carter, Lukas M.; Brockman, John D.; Loyalka, Sudarshan K.
  • Journal of Radioanalytical and Nuclear Chemistry, Vol. 307, Issue 3
  • DOI: 10.1007/s10967-015-4633-0

First high temperature safety tests of AGR-1 TRISO fuel with the Fuel Accident Condition Simulator (FACS) furnace
journal, September 2015


Fuel accident performance testing for small HTRs
journal, April 1990


Diffusion of cesium and iodine in compressed IG-110 graphite compacts
journal, August 2016


ICP-MS measurement of silver diffusion coefficient in graphite IG-110 between 1048K and 1284K
journal, January 2018


Numerical Study on Hydrogen Flow Behavior in Two Compartments with Different Connecting Pipes
journal, January 2017

  • Liu, HanChen; Cao, XueWu
  • Science and Technology of Nuclear Installations, Vol. 2017
  • DOI: 10.1155/2017/4709503

Key results from irradiation and post-irradiation examination of AGR-1 UCO TRISO fuel
journal, April 2018


Coated particle fuel: Historical perspectives and current progress
journal, March 2019