The spatial distribution of thermal neutrons in a reactor lattices cell is of fundamental importance for many reasons. First of all, this information allows the determination of the relative absorption rates in each component of the cell which in turn enables a determination of the thermal utilization, and the diffusion length of the lattice. In addition, the observed spatial distributions of thermal neutrons in the lattice cell is of major interest in testing various approximations to the solution of the transport equation such as the P1 and P3 solutions
Fission track registration technique is being extensively used for many practical applications in nu...
Cribier Daniel. La diffusion inélastique des neutrons. In: Bulletin de la Société française de Minér...
M.Phil. (Energy Studies)SAFARI-1 is a 20 MW research reactor, which is over 45 years old, and is exp...
"Operated by the University of Chicago under Contract W-31-109-eng-38.""Metallurgy Division Program ...
Measurements were made in the Process Revelopment Pile (PDP) of the distribution of the thermal neut...
On applique la méthode d'autoradiographie à l'étude de la distribution des neutrons thermiques dans ...
This report supersedes sections of the following ANL Metallurgy Division Quarterly Reports: ANL-5489...
Methods are developed for estimating the effect on a critical assembly of fabricating it as a lattic...
The primary purpose of these experiments was to measure the spatial distribution of neutron flux and...
The paper considers the influence of the spatial grid type on the result of solving the equation of ...
A 4-energy multigroup calculation of neutron reaction rates for absorption, fission,n*fission nuclea...
The neutron flux distributions in an EGCR cell containing seven and clusters of 2.0 and 2.6a enriche...
Under the general heading of Reactor Lattices are reported a new method of calculating resonance esc...
In this report the problem is considered of determining neutron flux distributions in reactors consi...
The neutron diffusion equation was solved under a “single cylinder one group (thermal neutrons)” app...
Fission track registration technique is being extensively used for many practical applications in nu...
Cribier Daniel. La diffusion inélastique des neutrons. In: Bulletin de la Société française de Minér...
M.Phil. (Energy Studies)SAFARI-1 is a 20 MW research reactor, which is over 45 years old, and is exp...
"Operated by the University of Chicago under Contract W-31-109-eng-38.""Metallurgy Division Program ...
Measurements were made in the Process Revelopment Pile (PDP) of the distribution of the thermal neut...
On applique la méthode d'autoradiographie à l'étude de la distribution des neutrons thermiques dans ...
This report supersedes sections of the following ANL Metallurgy Division Quarterly Reports: ANL-5489...
Methods are developed for estimating the effect on a critical assembly of fabricating it as a lattic...
The primary purpose of these experiments was to measure the spatial distribution of neutron flux and...
The paper considers the influence of the spatial grid type on the result of solving the equation of ...
A 4-energy multigroup calculation of neutron reaction rates for absorption, fission,n*fission nuclea...
The neutron flux distributions in an EGCR cell containing seven and clusters of 2.0 and 2.6a enriche...
Under the general heading of Reactor Lattices are reported a new method of calculating resonance esc...
In this report the problem is considered of determining neutron flux distributions in reactors consi...
The neutron diffusion equation was solved under a “single cylinder one group (thermal neutrons)” app...
Fission track registration technique is being extensively used for many practical applications in nu...
Cribier Daniel. La diffusion inélastique des neutrons. In: Bulletin de la Société française de Minér...
M.Phil. (Energy Studies)SAFARI-1 is a 20 MW research reactor, which is over 45 years old, and is exp...