Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Theron D. Marshall"'
Autor:
Changhu Xing, Casey J. Jesse, Warren F. Jones, Maxine P. Johnson, Ann Marie Phillips, Theron D. Marshall
Publikováno v:
Nuclear Science and Engineering. :1-12
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::078ac7fb5871780591277a33cd467e4f
https://doi.org/10.1080/00295639.2022.2153599
https://doi.org/10.1080/00295639.2022.2153599
Autor:
Changhu Xing, Casey J. Jesse, Warren F. Jones, Maxine P. Johnson, Ann Marie Phillips, Theron D. Marshall
Publikováno v:
Nuclear Engineering and Design. 395:111857
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d8cb126b7a8782521106891da732ab09
https://doi.org/10.1016/j.nucengdes.2022.111857
https://doi.org/10.1016/j.nucengdes.2022.111857
Publikováno v:
Fusion Technology. 39:849-855
A conclusive safety assessment of a fusion reactor requires that the thermal response of the divertor assembly is known with a high degree of accuracy. Such accuracy is mandated because the divertor assembly is subjected to the highest levels of inci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bce9c671d4719c49353262bf59d37389
https://doi.org/10.13182/fst01-a11963345
https://doi.org/10.13182/fst01-a11963345
Publikováno v:
Fusion Technology. 37:38-53
This paper discusses the thermal response of two prototypical International Thermonuclear Experimental Reactor (ITER) divertor channels during simulated loss-of-flow-accident (LOFA) experiments. The thermal response was characterized by the time-to-b
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b0a3e7313dd298fd00db7d71689fd18
https://doi.org/10.13182/fst00-a120
https://doi.org/10.13182/fst00-a120
Publikováno v:
Nuclear Technology. 114:84-96
Probabilistic risk assessment methodology is applied to generate an evaluation of the relative likelihood of safe recovery following selected pressurized water reactor (PWR) design basis accidents for a Russian V213 nuclear power reactor. US-designed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8efc3b447465ea7412a8872a08c3088b
https://doi.org/10.13182/nt96-a35225
https://doi.org/10.13182/nt96-a35225
Autor:
Kenneth Czerwinski, Michael J. Driscoll, Pavel Hejzlar, Michael J. Pope, Kevan D. Weaver, James R. Parry, Theron D. Marshall, Dan Wachs, Peter Yarsky, Cliff B. Davis
This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics;
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d645bac87e568e6340e0aa585dba9fc7
https://doi.org/10.2172/839251
https://doi.org/10.2172/839251
Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems: Annual and Final Report
The Idaho National Laboratory (INL) contribution to the Nuclear Energy Research Initiative (NERI) project number 2002-005 was divided into reactor physics, and thermal-hydraulics and plant design. The research targeted credible physics and thermal-hy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1a6ad70049ea3b9ba0568ac5711480ce
https://doi.org/10.2172/911594
https://doi.org/10.2172/911594
Autor:
Cliff B. Davis, Dustin Crawford, Kenneth Czerwinski, Theron D. Marshall, Thomas Hartmann, Mike Driscoll, Pavel Hejzlar, Michael J. Pope, Dan Wachs, Peter Yarsky, Pradip Saha, James R. Parry, Kevan D. Weaver
This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics;
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::69906239c46935807ae5ccad077b7f24
https://doi.org/10.2172/836633
https://doi.org/10.2172/836633
Publikováno v:
Proceedings of 16th International Symposium on Fusion Engineering.
In an off-normal event, water-cooled copper divertor plates in the International Thermonuclear Experimental Reactor (ITER) may either experience heat loads beyond their design basis, or the normal heat lends may be accompanied by low coolant pressure
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::935866c268156c80d605c5e0870cf6fb
https://doi.org/10.1109/fusion.1995.534204
https://doi.org/10.1109/fusion.1995.534204
Autor:
Dennis L. Youchison, J.M. McDonald, Lee C. Cadwallader, Robert D. Watson, Theron D. Marshall, L.S. Wold
Publikováno v:
Proceedings of 16th International Symposium on Fusion Engineering.
The Loss of Flow Accident (LOFA) is a serious safety concern for the International Thermonuclear Experimental Reactor (ITER) as it has been suggested that greater than 100 seconds are necessary to safely shutdown the plasma when ITER is operating at
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8318d9519fb0cdda0f8319d574f3a6a4
https://doi.org/10.1109/fusion.1995.534209
https://doi.org/10.1109/fusion.1995.534209