THERMIT-2 : a two-fluid model for light water reactor subchannel transient analysis

THERMIT-2 : a two-fluid model for light water reactor subchannel transient analysis

Bibliographic Details
Main Authors:	Kelly, J. E., Kao, S. P., Kazimi, Mujid S.
Other Authors:	Boston Edison Company.
Published:	Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1981 2011
Subjects:	Light water reactors. Nuclear fuel elements
Online Access:	http://hdl.handle.net/1721.1/60460

Similar Items

User's guide for THERMIT-2 : a version of THERMIT for both core-wide and subchannel analysis of light water reactors
by: Kelly, J. E., et al.
Published: (2011)

Development and testing of three dimensional, two-fluid code THERMIT for LWR core and subchannel applications
by: Kelly, John Edward, et al.
Published: (2006)

Development of a two-fluid, two-phase model for light water reactor subchannel analysis
by: Kelly, J. E
Published: (2005)

Development of a three-dimensional two-fluid code with transient neutronic feedback for LWR applications
by: Griggs, D. P., et al.
Published: (2011)

An Introduction to the THERMIT thermal hydraulic reactor computer codes at M.I.T.
by: Parsons, Donald Kent, et al.
Published: (2014)

Development of models for the sodium version of the two-phase three dimensional thermal hydraulics code THERMIT
by: Wilson, Gregory James, et al.
Published: (2006)

Availability of the THERMIT thermal hydraulic reactor computer codes through M.I.T.
by: Parsons, Donald Kent, et al.
Published: (2014)

Axial and transverse momentum balance in subchannel analysis.
by: Bartzis, John George
Published: (2005)

Analysis of forced convection degraded core cooling in light water reactors
by: Mohammed, S. M., et al.
Published: (2014)

Development of a method for BWR subchannel analysis.
by: Faya, Artur José Goncalves
Published: (2005)

Development of a method for BWR subchannel analysis
by: Faya, Artur José Goncalves, et al.
Published: (2006)

WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles.
by: Wolf, Lothar, et al.
Published: (2006)

22.251 / 22.351 Systems Analysis of the Nuclear Fuel Cycle, Fall 2005
by: Kazimi, Mujid S.
Published: (2005)

Reactor core thermal-hydraulic analysis ; improvement and application of the code COBRA-IIICMIT
by: Loomis, James N., et al.
Published: (2011)

WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. Volume II. User's Manual
by: Guillebaud, Louis Jean Marie., et al.
Published: (2006)

WOSUB : a subchannel code for steady-state and transient thermal-hydraulic analysis of BWR fuel pin bundles. Volume III. Assessment and Comparison
by: Wolf, Lothar, et al.
Published: (2006)

A two dimensional, two fluid model for sodium boiling in LMFBR fuel assemblies
by: Granziera, Mario Roberto, et al.
Published: (2006)

Theoretical studies on some aspects of molten fuel-coolant thermal interaction
by: Kazimi, Mujid S.
Published: (2014)

A condensed review of nuclear reactor thermal-hydraulic computer codes for two-phase flow analysis
by: Kazimi, Mujid S., et al.
Published: (2006)

Assessment of thorium blankets for fast breeder reactors
by: Wood, Paul Joseph, et al.
Published: (2014)

Performance of light water reactor fuel rods during plant power changes
by: Rivera, John Edward
Published: (2005)

An evaluation of the fast-mixed spectrum reactor
by: Loh, Wee Tee
Published: (2010)

Fabrication of water reactor fuel elements : proceedings
by: International Symposium on Water Reactor Fuel Element Fabrication with Special emphasis on the Effect of Fabrication Technology on Fuel Performance (1978 : Prague)
Published: (1979)

Analysis of design strategies for mitigating the consequences of lithium fire within containment of controlled thermonuclear reactors
by: Dube, Donald A., et al.
Published: (2014)

Analysis of strategies for improving uranium utilization in pressurized water reactors
by: Sefcik, Joseph A., et al.
Published: (2011)

Thermal-hydraulic analysis of tight lattice light water reactors.
by: Boyd, William Artis
Published: (2005)

Optimization of the axial power shape in pressurized water reactors
by: Melik, M. A.
Published: (2011)

Reactor core fuel management /
by: Silvennoinen, P
Published: (1976)

The differential radiological impact of plutonium recycle in the light-water reactor fuel cycle : effluent discharges during normal operation /
by: Bouville, A., et al.
Published: (1980)

Reactor burn-up physics : proceedings/
by: 5898 International Atomic Energy Agency. Panel on Reactor Burn-up Physics
Published: (1973)

Fuel element performance maps for nuclear reactor operational decisions.
by: Da Silva, Othon Luiz Pinheiro
Published: (2010)

Materials ageing and degradation in light water reactors : mechanisms and management /
by: Murty, K. L. 544195
Published: (2013)

Light-water reactor physics parameters for transient analysis
by: Olmos, Jaime, et al.
Published: (2005)

An evaluation of the breed/burn fast reactor concept
by: Atefi, Bahman
Published: (2010)

Spatial homogenization methods for light water reactor analysis
by: Smith, Kord Sterling
Published: (2005)

Application of probabilistic consequence analysis to the assessment of potential radiological hazards of fusion reactors
by: Sawdye, Robert William, et al.
Published: (2014)

Fluid fuel reactors /
by: Lane, James A., et al.
Published: (1958)

On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor—A Neutron Physical Study
by: Bruno Merk, et al.
Published: (2015-11-01)

Optimization of the axial power shape in pressurized water reactors
by: Melik, M. A
Published: (2005)

Technology Selection for Offshore Underwater Small Modular Reactors
by: Koroush Shirvan, et al.
Published: (2016-12-01)