Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Dawn M. Scates"'
Autor:
Dawn M. Scates, Blaise P. Collin, Grant L. Hawkes, James W. Sterbentz, Binh T. Pham, David A. Petti, Paul A. Demkowicz, Joe Palmer
Publikováno v:
Nuclear Engineering and Design. 327:212-227
AGR-3/4 was the combined third and fourth planned irradiations for the U.S. Department of Energy (DOE) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The primary purpose of the AGR program is to support the development and qua
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d9c9f76b21cc8b36956a3859f9d9672f
https://doi.org/10.1016/j.nucengdes.2017.12.016
https://doi.org/10.1016/j.nucengdes.2017.12.016
Autor:
Grant L. Hawkes, David A. Petti, Douglas E. Stacey, Binh T. Pham, James W. Sterbentz, Dawn M. Scates, Paul A. Demkowicz, Blaise P. Collin
Publikováno v:
Annals of Nuclear Energy. 150:107833
UCO and UO2 tristructural isotropic fuel compacts were irradiated in the AGR-2 experiment, conducted in the Advanced Test Reactor for 559.2 effective full power days. UCO and UO2 compacts reached calculated peak burnups of 13.15 and 10.69% fissions p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ca41752b198b3c8ddbca56220346447b
https://doi.org/10.1016/j.anucene.2020.107833
https://doi.org/10.1016/j.anucene.2020.107833
Publikováno v:
Nuclear Engineering and Design. 306:14-23
A series of advanced gas reactor (AGR) irradiation tests is being conducted in the advanced test reactor (ATR) at Idaho National Laboratory (INL) in support of development and qualification of tristructural isotropic (TRISO) fuel used in the High tem
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::fb6ed1d2bf3cb14303e58caf1d743c9b
Publikováno v:
Nuclear Engineering and Design. 358:110417
The AGR-5/6/7 test is a fueled multiple-capsule experiment currently being irra- diated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). AGR-5/6/7 is the fourth and last experiment in the “AGR-experiment” series which is bei
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f53d288a7a066952151e152190da6125
https://doi.org/10.1016/j.nucengdes.2019.110417
https://doi.org/10.1016/j.nucengdes.2019.110417
Publikováno v:
Journal of Nuclear Materials. 464:320-330
Three TRISO fuel compacts from the AGR-1 irradiation experiment were subjected to safety tests at 1600 and 1800 °C for approximately 300 h to evaluate the fission product retention characteristics. Silver behavior was dominated by rapid release of a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9ab0b382031fe96985a7b97f885c55bc
https://doi.org/10.1016/j.jnucmat.2015.05.006
https://doi.org/10.1016/j.jnucmat.2015.05.006
Publikováno v:
Nuclear Engineering and Design. 271:231-237
The AGR-1 Advanced Gas Reactor (AGR) tristructural-isotropic-particle fuel experiment underwent 13 irradiation intervals from December 2006 until November 2009 within the Idaho National Laboratory Advanced Test Reactor in support of the Next Generati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::55709239a59268d2186a992176a2c9e5
https://doi.org/10.1016/j.nucengdes.2013.11.037
https://doi.org/10.1016/j.nucengdes.2013.11.037
Autor:
Dawn M. Scates, Jason M. Harp, David V. Laug, John B. Walter, Edward L. Reber, Lyle G. Roybal, Robert Noel Morris, Paul A. Demkowicz
Publikováno v:
Nuclear Engineering and Design. 251:164-172
The AGR-1 irradiation of TRISO-coated particle fuel specimens was recently completed and represents the most successful such irradiation in US history, reaching peak burnups of greater than 19% FIMA with zero failures out of 300,000 particles. An ext
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6d308ee5c3ed5719d79403ebf321087c
https://doi.org/10.1016/j.nucengdes.2011.10.048
https://doi.org/10.1016/j.nucengdes.2011.10.048
A series of Advanced Gas Reactor (AGR) irradiation tests is being conducted in the Advanced Test Reactor at Idaho National Laboratory in support of development and qualification of tristructural isotropic (TRISO) low enriched fuel used in the High Te
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::517d75e2d1831c711c9d2002c70cb34f
https://doi.org/10.2172/1168622
https://doi.org/10.2172/1168622
