Calculations of several important neutronic parameters have been performed for ten different three-element configurations considered for the Advanced Neutron Source (ANS) Reactor. Six of these configurations (labeled ST, SB, MT, MB, LT, and LB) are there result of the permutations of the same three elements. Two configurations (ST- MOD and SB-MOD) have the same element configuration as their base core design (ST and SB) but have slightly different element dimensions, and two configurations (ST-OL1 and ST-OL2) have two overlapping elements to increase the neutron fluxes in the reflector. For each configuration, in addition to the conceptual two-element design, fuel-cycle calculations were performed with calculations required to obtain unpert...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
Several fusion power plant design studies were made at a number of universities and laboratories in ...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
The proposed Advanced Neutron Source (ANS) pre-conceptual design consists of a two-element 330 MW{su...
Source of neutrons in the proposed Advanced Neutron Source facility is a multipurpose research react...
This report summarizes the neutronics analysis performed during 1991 and 1992 in support of characte...
In order to utilize reduced enrichment fuel, the three-element-core design for the Advanced Neutron ...
Two-dimensional discrete ordinates radiation transport calculations were performed for a model of th...
A summary of the methods and models used to perform neutronics analyses on the Advanced Neutron Sour...
The Fluoride High-Temperature Reactor (FHR) and the Very High-Temperature Reactor (VHTR) are advance...
AbstractMixed nitride uranium–plutonium fuel is the most attractive and advanced type of fuel for fa...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
Several fusion power plant design studies were made at a number of universities and laboratories in ...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
The proposed Advanced Neutron Source (ANS) pre-conceptual design consists of a two-element 330 MW{su...
Source of neutrons in the proposed Advanced Neutron Source facility is a multipurpose research react...
This report summarizes the neutronics analysis performed during 1991 and 1992 in support of characte...
In order to utilize reduced enrichment fuel, the three-element-core design for the Advanced Neutron ...
Two-dimensional discrete ordinates radiation transport calculations were performed for a model of th...
A summary of the methods and models used to perform neutronics analyses on the Advanced Neutron Sour...
The Fluoride High-Temperature Reactor (FHR) and the Very High-Temperature Reactor (VHTR) are advance...
AbstractMixed nitride uranium–plutonium fuel is the most attractive and advanced type of fuel for fa...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
The new spirit and urgency of converting the remaining research reactors from highly enriched uraniu...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...
Several fusion power plant design studies were made at a number of universities and laboratories in ...
An advanced computational tool based on Monte Carlo code was developed for the neutronic analysis of...