Several concepts of new reactors use graphite. Some of them use graphite as a moderator, some of them as a reflector. There are at least two concepts of these graphitetype reactors under development in the Czech Republic. Both reactors use graphite as the reflector. An in-core measurement might be impossible to use because of various reasons, for instance, high temperature or aggressive environment. Therefore, this article focuses on ex-core neutron flux measurement system placed in the graphite reflector and the optimization of ex-core detector position. A set of experiments were performed at LR-0 reactor. The LR-0 is a light water reactor with a well-defined neutron field, which can be used for different material insertion tests and testi...
Graphite is widely used as a moderator, reflector, and fuel matrix in various types of nuclear react...
A very brief review of radiation effects in graphite is given followed by projections of graphite be...
The Next Generation Nuclear Plant Project Graphite Research and Development program is currently est...
Several concepts of new reactors use graphite. Some of them use graphite as a moderator, some of the...
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given t...
An ex-core neutron flux measurement is a crucial system for all common power reactors. It is necessa...
An ex-core neutron flux measurement is a crucial system for all common power reactors. It is necessa...
Nowadays, there is an increasing demand for new SMR reactors with a wide range of applications, ofte...
Graphite is an often-used moderating material on the basis of its good moderating power and very low...
In graphite-reflected thermal reactors, even a detector placed far from fuel region may detect a cer...
Diplomová práce věnuje charakterizaci neutronového pole ve speciální grafitové vložné zóně reaktoru ...
The Japan Atomic Energy Agency (JAEA) started the Research and Development (R&D) to improve nuclear ...
A review of the experimental data for natC(n,c) and 12C(n,c) was made to identify the origin of the ...
Gas-cooled, graphite-moderated nuclear reactors suffer ageing and degradation to the graphite during...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
Graphite is widely used as a moderator, reflector, and fuel matrix in various types of nuclear react...
A very brief review of radiation effects in graphite is given followed by projections of graphite be...
The Next Generation Nuclear Plant Project Graphite Research and Development program is currently est...
Several concepts of new reactors use graphite. Some of them use graphite as a moderator, some of the...
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given t...
An ex-core neutron flux measurement is a crucial system for all common power reactors. It is necessa...
An ex-core neutron flux measurement is a crucial system for all common power reactors. It is necessa...
Nowadays, there is an increasing demand for new SMR reactors with a wide range of applications, ofte...
Graphite is an often-used moderating material on the basis of its good moderating power and very low...
In graphite-reflected thermal reactors, even a detector placed far from fuel region may detect a cer...
Diplomová práce věnuje charakterizaci neutronového pole ve speciální grafitové vložné zóně reaktoru ...
The Japan Atomic Energy Agency (JAEA) started the Research and Development (R&D) to improve nuclear ...
A review of the experimental data for natC(n,c) and 12C(n,c) was made to identify the origin of the ...
Gas-cooled, graphite-moderated nuclear reactors suffer ageing and degradation to the graphite during...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
Graphite is widely used as a moderator, reflector, and fuel matrix in various types of nuclear react...
A very brief review of radiation effects in graphite is given followed by projections of graphite be...
The Next Generation Nuclear Plant Project Graphite Research and Development program is currently est...