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pro vyhledávání: '"N.J. Lombardo"'
This report describes and presents data from a severe fuel damage test that was conducted in the National Research Universal (NRU) reactor at Chalk River Nuclear Laboratories (CRNL), Ontario, Canada. The test, designated FLHT-5, was the fourth in a s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c0f78dbb0063e4f85537e4fe4789014b
https://doi.org/10.2172/10188341
https://doi.org/10.2172/10188341
This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the Full-Length High Temperature Experiment-5 (FLHT-5) to be conducted in the L-24 position of the National Research Universal (NRU) Re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::052460a4d4cfc3c9d5cbbbc0f1cec9a7
https://doi.org/10.2172/10194763
https://doi.org/10.2172/10194763
Autor:
N.J. Lombardo, F.E. Panisko, L. J. Parchen, L. L. King, J.P. Pilger, G.M. Hesson, W.N. Rausch, D.E. Hurley
Hazardous conditions associated with performing the Full-Length High- Temperature (FLHT). Severe Fuel Damage Test No. 2 experiment have been analyzed. Major hazards that could cause harm or damage are (1) radioactive fission products, (2) radiation f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6dc263aded3353d0b9393d8a798e2077
https://doi.org/10.2172/10189926
https://doi.org/10.2172/10189926
This strategy plan describes a coupled analytical/experimental approach to develop a multi-functional scarifier end effector coupled with a pneumatic conveyance system to retrieve wastes from underground storage tanks. The scarifier uses ultra-high-p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be521317d64ccc826e5a86f475a3fb3e
https://doi.org/10.2172/10181268
https://doi.org/10.2172/10181268
This document presents an assessment of the severe accident phenomena observed from four Full-Length High-Temperature (FLHT) tests that were performed by the Pacific Northwest Laboratory (PNL) in the National Research Universal (NRU) reactor at Chalk
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::98946a441cf4a4408216c4380c2862fa
https://doi.org/10.2172/7042819
https://doi.org/10.2172/7042819
TRUMP-BD (Boil Down) is an extension of the TRUMP (Edwards 1972) computer program for the analysis of nuclear fuel assemblies under severe accident conditions. This extension allows prediction of the heat transfer rates, metal-water oxidation rates,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e9e79592b1f47d3bf6035ef7481125e5
https://doi.org/10.2172/6834315
https://doi.org/10.2172/6834315
COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Depa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3428de75a2887cb165395e8a39320db7
https://doi.org/10.2172/6928785
https://doi.org/10.2172/6928785
Autor:
N.J. Lombardo, L.L. Eyler
The objective of the Hydrotransport Plugging Study is to investigate phenomena associated with predicting the onset and occurrence of plugging in pipeline transport of coal. This study addresses large particle transport plugging phenomena that may be
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::47c51f23bd854c278f7ab8e70dde17ec
https://doi.org/10.2172/5650814
https://doi.org/10.2172/5650814
This report presents the results of the COBRA-SFS (Spent Fuel Storage) computer code validation effort. COBRA-SFS, while refined and specialized for spent fuel storage system analyses, is a lumped-volume thermal-hydraulic analysis computer code that
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33cda1424808233df2d54111ee5de975
https://doi.org/10.2172/6883584
https://doi.org/10.2172/6883584