Zobrazeno 1 - 10
of 46
pro vyhledávání: '"Lance J. Agee"'
Publikováno v:
Nuclear Technology. 148:25-34
As part of an overall verification and validation effort, the Electric Power Research Institute's (EPRIs) CORETRAN-01 has been benchmarked against Northern States Power's Prairie Island and Monticello reactors through 12 cycles of operation. The two
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8b1bb3ee5c269d73147a51656cbb2d5f
https://doi.org/10.13182/nt04-a3545
https://doi.org/10.13182/nt04-a3545
Autor:
Lance J. Agee
Publikováno v:
Nuclear Technology. 142:3-9
The nuclear industry’s current “vision” for 2020 is for growth in U.S. nuclear to a 23% share of generation in 2020. To support this vision, the Electric Power Research Institute’s Nuclear Power Di...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::295e8cf0d68758c8dd4054b62bc6f775
https://doi.org/10.13182/nt03-a3369
https://doi.org/10.13182/nt03-a3369
Publikováno v:
Nuclear Technology. 142:64-76
This paper presents an evaluation of many of the RETRAN-3D two-phase pressure drop and heat transfer models by comparing model prediction to a large body of experimental data.RETRAN-3D has been use...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::69d2f5afab64be2917401189ea6bd3e1
https://doi.org/10.13182/nt03-a3374
https://doi.org/10.13182/nt03-a3374
Autor:
Antonio F. Dias, Nicholas G. Trikouros, Lance J. Agee, Ardesar Irani, John G. Shatford, Craig E. Peterson
Publikováno v:
Nuclear Technology. 128:233-244
A main-steam-line-break accident analysis for Three Mile Island Unit I is performed with point kinetics and three-dimensional kinetics with RETRAN-3D MOD002. These analyses were performed to demonstrate differences in results that can be expected due
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1653f1267fa052d4a315949ebb8e6ed
https://doi.org/10.13182/nt99-a3028
https://doi.org/10.13182/nt99-a3028
Publikováno v:
Nuclear Technology. 122:132-145
A RETRAN-03 computer code version has been developed to analyze reactor transients requiring three-dimensional reactor core neutronics models. The new code will enable the user to couple a complex RETRAN nuclear steam supply system model to a detaile
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::67a326c2dd731f8d048c1d678bb1b8d1
https://doi.org/10.13182/nt98-a2857
https://doi.org/10.13182/nt98-a2857
Publikováno v:
Nuclear Technology. 122:170-178
Reported fuel failures at low peak enthalpies for highly exposed fuel during fast reactivity transients promoted the evaluation of reactivity insertion accidents (RIAs) in light water reactors with...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::952d2cb1859baac2ccb095f9f7e26d74
https://doi.org/10.13182/nt98-a2860
https://doi.org/10.13182/nt98-a2860
Autor:
Lance J. Agee
Publikováno v:
Nuclear Technology. 121:229-236
An overview is presented of the important RETRAN-related events that have occurred since the previous International RETRAN Conference, which was held in 1991. Summarized are the following: (a) an overview of the Electric Power Research Institute's (E
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::386b35f32ca58e944e60b2b58a21c2bc
https://doi.org/10.13182/nt98-a2835
https://doi.org/10.13182/nt98-a2835
Publikováno v:
Nuclear Technology. 121:346-358
The rod ejection accident in a pressurized water reactor and the control rod drop accident in a boiling water reactor are analyzed in this paper, both in a best-estimate (realistic) and a conservative manner. CORETRAN, a modem three-dimensional time-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1d6a00d5d2cb31c7cd1cb0ba41eac6ce
https://doi.org/10.13182/nt98-a2846
https://doi.org/10.13182/nt98-a2846
Publikováno v:
Nuclear Technology. 112:346-354
The estimation of critical heat flux (CHF) in nuclear reactors is based largely on empirical relations that have a physical limiting conditions, a narrow range of applicability, and are inadequate for transient conditions. It is generally agreed that
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::263a5ce6e1d84047aeb3c134c783af99
https://doi.org/10.13182/nt95-a35160
https://doi.org/10.13182/nt95-a35160
Publikováno v:
Nuclear Technology. 100:162-173
Boiling water reactors (BWRs) are susceptible to thermal-hydraulic instabilities that must be considered in BWR design and operation. Early BWRs were designed to be very stable while operating unde...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::94e3402d6688f1e759eadcc0b865df14
https://doi.org/10.13182/nt92-a34739
https://doi.org/10.13182/nt92-a34739