Zobrazeno 1 - 10
of 41
pro vyhledávání: '"I.K. Madni"'
Autor:
I.K. Madni, Xiao-Dong Guo
Publikováno v:
Nuclear Technology. 99:203-212
The MELCOR computer code has been used to simulate the National Research Universal full-length high-temperature 2 (FLHT-2) test. Input data for the analysis were obtained from the FLHT-2 test Data Report and from SCDAP input. In this paper results ar
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2852dff0337e86e00cc23cc1a52a3511
https://doi.org/10.13182/nt92-a34690
https://doi.org/10.13182/nt92-a34690
Publikováno v:
Nuclear Technology. 90:63-77
A simplified approach has been developed to calculate uncertainties in early off-site consequences from nuclear reactor accidents. The consequence model (SMART) is based on a solution procedure that uses simplified meteorology and involves direct ana
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::68842a85981b149a6034621570b4e6a1
https://doi.org/10.13182/nt90-a34386
https://doi.org/10.13182/nt90-a34386
Autor:
I.K. Madni
MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratorie
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c6da16df8deb24bdcbd3850e0b8e6b22
https://doi.org/10.2172/115097
https://doi.org/10.2172/115097
Autor:
I.K. Madni
This report documents the results from MELCOR calculations of the Long-Term Station Blackout Accident Sequence, with failure to depressurize the reactor vessel, at the Peach Bottom (BWR Mark I) plant, and presents comparisons with Source Term Code Pa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c1b239ed4fd47930ae1973be5adb8ae3
https://doi.org/10.2172/10159734
https://doi.org/10.2172/10159734
Autor:
J.W. Baum, G.A. Greene, J.C. Higgins, W. Wulff, C.B. Meinhold, A.J. Philippacoupoulos, A. Azarm, D.J. Diamond, J.H. Taylor, T.A. Khan, A.J. Weiss, W.T. Pratt, H.P. Nourbakhsh, N.K. Tutu, R.W. Youngblood, S.B. Haber, J. O'Hara, T. Ginsberg, J.R. Lehner, G.J. Van Tuyle, P. Samanta, R. Fitzpatrick, I.K. Madni
This progress report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the Division of Regulatory Applications, Division of Engineering, Division of Safety Issue Resolution, and Divisio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a8bac6144534591d28b7820881a80a94
https://doi.org/10.2172/6835736
https://doi.org/10.2172/6835736
Publikováno v:
Nuclear Engineering and Design. 66:437-446
The decay heat removal capability of LMFBR plants is inverstigated in two steps: the transition phase and the established phase of natural circulation. Major parameters affecting the transition phase are briefly reviewed. This paper, then, considers
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::96ec9d5ab50e40e4796b19f38df0acb5
https://doi.org/10.1016/0029-5493(81)90173-4
https://doi.org/10.1016/0029-5493(81)90173-4
Autor:
Ashok K. Agrawal, I.K. Madni
Publikováno v:
Nuclear Engineering and Design. 62:199-218
In discussing LMFBR thermal-hydraulic analysis, this paper focuses on the heat transport system and its impact on the predicted core behavior, particularly during off-normal or protected accident transients. Following a brief background of related wo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7c87520b30f77fdc5d52ba154b064b41
https://doi.org/10.1016/0029-5493(80)90029-1
https://doi.org/10.1016/0029-5493(80)90029-1
Autor:
E.G. Cazzoli, I.K. Madni
Models for components and processes that are needed for simulation of thermohydraulic transient in a pool-type liquid metal fast breeder reactor (LMFBR) plant are described in this report. A computer code, SSC-P, has been developed as a part of the S
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e66680ba3b264e6ab7d5d890eeaaa10d
https://doi.org/10.2172/5094081
https://doi.org/10.2172/5094081
A personal computer-based model, SMART, has been developed that uses an integral approach for calculating early offsite consequences from nuclear reactor accidents. The solution procedure uses simplified meteorology and involves direct analytic integ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ea23d24513257bf3afab1baef5ce95b3
https://doi.org/10.2172/6945262
https://doi.org/10.2172/6945262
Autor:
E. Cazzoli, I.K. Madni
A single-phase pump model for transient and steady-state analysis of LMFBR heat transport systems is presented. Fundamental equations of the model are angular momentum balance to determine transient impeller speed and mass balance (including thermal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e64e0020ff0b7c7feec9daf9c505afdd
https://doi.org/10.2172/6594526
https://doi.org/10.2172/6594526