Abstract FEMLAB has played a key role in the design and safety analysis of several key components of the new High Flux Isotope Reactor (HFIR) hydrogen (H2) cold neutron source (CS) at Oak Ridge National Laboratory (ORNL). The main components of interest for the detailed analysis capability of FEMLAB are those where the H2 temperature spans a large range causing the fluid proper-ties to change dramatically in both magnitude and slope. This dramatic fluid property change tends to aggravate the problem solution as if it were a two-phase fluid, yet be-cause the pressure is supercritical, is actually only a sin-gle phase. Two HFIR CS components that are designed to experience this dramatic fluid property change are the moderator vessel (MV) and ...
4siIn this study, thermal-hydraulic parameters inside the containment of a WWER-1000/v446 nuclear po...
This paper deals with hydrogen production in nuclear power reactors by cladding of the fuel. The des...
This paper deals with hydrogen production in nuclear power reactors by cladding of the fuel. The des...
A project is underway at Oak Ridge National Laboratory (ORNL) to design, test, and install a cold ne...
Following the decision to cancel the Advanced Neutron Source (ANS) Project at Oak Ridge National Lab...
In February 1995, Oak Ridge National Laboratory`s (ORNL`s) deputy director formed a group to examine...
The flow field distribution and thermal properties of supercritical hydrogen are crucial factors aff...
In February 1995, the deputy director of Oak Ridge National Laboratory (ORNL) formed a group to exam...
High-energy neutrons are being decelerated by passing through supercritical parahydrogen circulated ...
The design of the High-Flux Isotope Reactor (HFIR) was supported by a series of preliminary experime...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
In this master thesis, cold moderator flow concepts have been developed on behalf of the European Sp...
Following termination of the Advanced Neutron Source (ANS) Project, a program of upgrades to the Dep...
The computational ability to accurately predict the conditions in an experiment under irradiation is...
Pipe height in cylindrical neutron moderator is an important factor to flow pattern, temperature dis...
4siIn this study, thermal-hydraulic parameters inside the containment of a WWER-1000/v446 nuclear po...
This paper deals with hydrogen production in nuclear power reactors by cladding of the fuel. The des...
This paper deals with hydrogen production in nuclear power reactors by cladding of the fuel. The des...
A project is underway at Oak Ridge National Laboratory (ORNL) to design, test, and install a cold ne...
Following the decision to cancel the Advanced Neutron Source (ANS) Project at Oak Ridge National Lab...
In February 1995, Oak Ridge National Laboratory`s (ORNL`s) deputy director formed a group to examine...
The flow field distribution and thermal properties of supercritical hydrogen are crucial factors aff...
In February 1995, the deputy director of Oak Ridge National Laboratory (ORNL) formed a group to exam...
High-energy neutrons are being decelerated by passing through supercritical parahydrogen circulated ...
The design of the High-Flux Isotope Reactor (HFIR) was supported by a series of preliminary experime...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
In this master thesis, cold moderator flow concepts have been developed on behalf of the European Sp...
Following termination of the Advanced Neutron Source (ANS) Project, a program of upgrades to the Dep...
The computational ability to accurately predict the conditions in an experiment under irradiation is...
Pipe height in cylindrical neutron moderator is an important factor to flow pattern, temperature dis...
4siIn this study, thermal-hydraulic parameters inside the containment of a WWER-1000/v446 nuclear po...
This paper deals with hydrogen production in nuclear power reactors by cladding of the fuel. The des...
This paper deals with hydrogen production in nuclear power reactors by cladding of the fuel. The des...