Zobrazeno 1 - 8
of 8
pro vyhledávání: '"D. K. Felde"'
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2003:367
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::156d869d10e2f9f6d35c6f6b3784e01c
https://doi.org/10.1299/jsmeicone.2003.367
https://doi.org/10.1299/jsmeicone.2003.367
This report presents experimental data and calculated steady-state and transient instrument uncertainties from the Oak Ridge National Laboratory Small Break LOCA Heat Transfer Test Series II. The subject test series was composed of six combined heat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3813abfcd7306225610ffbd784d693fd
https://doi.org/10.2172/5337631
https://doi.org/10.2172/5337631
Autor:
D. K. Felde
A design concept is presented for an in-bundle gamma densitometer system for measurement of subchannel average fluid density and void fraction in rod or tube bundles. This report describes (1) the application of the design concept to the Thermal-Hydr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::36184e31f01d04a071f3f934dc2b7229
https://doi.org/10.2172/5235507
https://doi.org/10.2172/5235507
Autor:
D K Felde
The heat and mass transport phenomena taking place in volumetrically-heated fluids have become of interest in recent years due to their significance in assessments of fast reactor safety and post-accident heat removal (PAHR). Following a hypothetical
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54bd57efa1fb868854060639343dbc69
https://doi.org/10.2172/6111111
https://doi.org/10.2172/6111111
Autor:
N C.J. Chen, D K Felde
An analysis of two-phase mass flux uncertainties for the Thermal-Hydraulic Test Facility (THTF) instrumented spool pieces is presented. Comparisons are made between various homogeneous mass flux models based on high-temperature and high-pressure wate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6787e735be5492df0138014c4666a12
https://doi.org/10.2172/5344067
https://doi.org/10.2172/5344067
The report presents experimental data and calculated steady-state and transient instrument uncertainties from Oak Ridge National Laboratory Small Break Loss of Coolant Accident (LOCA) Heat Transfer Test Series I. The subject test series was composed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::84dd314bff3ef0ca75b90db7412713f8
https://doi.org/10.2172/5337648
https://doi.org/10.2172/5337648
Following a hypothetical core disruptive accident (HCDA) in a fast reactor, the core debris may be in the form of a molten pool which is volumetrically heated by the radioactive decay of the dissolved fission products. The debris pool may be retained
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::05e610de1013ccfde1a5bc9bac026bd0
https://doi.org/10.2172/6109967
https://doi.org/10.2172/6109967