Results 11 to 20 of about 1,365 (205)

MELCOR Peer Review [PDF]

, 1992
MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. The newest version of MELCOR is Version 1.8.1, July 1991. MELCOR development has reached the point that the United States Nuclear Regulatory Commission sponsored a broad technical review by ...
Boyack, B. E., Dhir, V. K., Gieseke, J. A., Haste, T. J., Kenton, M. A., Khatib-Rahbar, M., Leonard, M. T., Viskanta, R.   +7 more
openaire   +4 more sources

MELCOR computer code manuals [PDF]

, 1995
MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code ...
Summers, R. M., Cole, R. K., Jr., Smith, R. C., Stuart, D. S., Thompson, S. L., Hodge, S. A., Hyman, C. R., Sanders, R. L.   +7 more
core   +6 more sources

Source Term Estimation under the SBLOCA-Induced Severe Accident Condition in the SMART

Science and Technology of Nuclear Installations, 2021
The SMART is a system-integrated modular reactor in which a nuclear steam supply system with a thermal power of 365 MW is contained inside of the reactor vessel.
Jaehyun Ham, Sang Ho Kim, Sung Il Kim, Byeonghee Lee, Jong-Hwa Park, Rae-Joon Park, Jaehoon Jung   +6 more
doaj   +2 more sources

Comparison of MAAP and MELCOR : and evaluation of MELCOR as a deterministic tool within RASTEP

, 2014
This master's thesis is an investigation and evaluation of MELCOR (a software tool for severe accident analyses regarding nuclear power plants), or more correctly of the (ASEA-Atom BWR 75) reactor model developed for version 1.8.6 of MELCOR. The main objective was to determine if MELCOR, with the reactor model in question, is able to produce ...
Sunnevik, Klas
core   +4 more sources

MELCOR Accident Analysis for ARIES-ACT [PDF]

Fusion Science and Technology, 2013
We model a loss of flow accident (LOFA) in the ARIES-ACT1 tokamak design. ARIES-ACT1 features an advanced SiC blanket with LiPb as coolant and breeder, a helium cooled steel structural ring and tungsten divertors, a thin-walled, helium cooled vacuum vessel, and a room temperature water-cooled shield outside the vacuum vessel.
Humrickhouse, Paul W., Merrill, Brad J.
core   +4 more sources

Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept [PDF]

Science and Technology of Nuclear Installations, 2015
As for Light Water Reactors (LWRs), one of the most challenging accidents for the future DEMOnstration power plant is the Loss of Coolant Accident, which can trigger the pressurization of the confinement structures and components. Hence, careful analyses
Bruno Gonfiotti, Sandro Paci
doaj   +2 more sources

Cancer incidence and outcomes registries in an Australian context: a systematic review

ANZ Journal of Surgery, Volume 93, Issue 10, Page 2314-2336, October 2023., 2023
Summary of identified Australian cancer registries and their purpose, inclusion criteria, and outcomes collected. Abstract Background Multiple cancer registries in Australia are used to track the incidence of cancer and the outcomes of their treatment.
Kit Chong, Jack Maida, Hwa Ian Ong, David Proud, James Lin, Adele Burgess, Alexander Heriot, Philip Smart, Helen Mohan   +8 more
wiley   +1 more source

Machine Learning Performance Prediction of a Solar Photovoltaic‐Thermoelectric System with Various Crystalline Silicon Cell Types

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
Since the solar photovoltaic‐thermoelectric (PV‐TE) is an upcoming technology, the current literature on PV‐TEs have failed to thoroughly investigate the effects of different solar cell types on the PV‐TE’s performance. Such parametric study becomes necessary since the properties of the solar cell, characterized by the cell temperature coefficient and ...
Hisham Alghamdi, Chika Maduabuchi, Abdullah Albaker, Abdulaziz Almalaq, Turki Alsuwian, Ibrahim Alatawi, Mahmoud Ahmed   +6 more
wiley   +1 more source

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal‐Hydraulic System Analysis Code

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
The external reactor vessel cooling provides a means to stabilize the molten core inside the reactor vessel during the severe accident in nuclear power plants. For a credible evaluation of the chances of success of in‐vessel melt retention, one requires high‐fidelity predictions on the natural circulation flow around the reactor vessel and, in ...
Yeon-Gun Lee, Il Woong Park, Geng Chen
wiley   +1 more source

Simulations of Core Damage Progression for TMI‐2 Severe Accident Using CINEMA Computer Code

Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023
As an integrated computer code development for severe accident sequence analysis in Korea, CINEMA has been developing from an initiation event to a containment failure. The CINEMA computer code is composed of CSPACE, SACAP, and SIRIUS, which are capable of simulating core melt progression with thermal hydraulic analysis of the RCS (reactor coolant ...
Rae-Joon Park, Donggun Son, Jun Ho Bae, Sung Won Bae, Bub-Dong Chung, Kwang Soon Ha, Han Zhang   +6 more
wiley   +1 more source