The United States is currently looking at options for handling of spent nuclear fuel. Currently, there are ≈ 70, 000 metric tons of spent fuel in storage in the US alone. Pyroprocessing is a possible method for spent nuclear fuel reprocessing which was proven to work at Argonne National Laboratory. This masters thesis showcases a method for empirically modeling hybrid k-edge densitometry, one of the numerous possible safeguards needed for a reprocessing facility. This is accomplished by using MCNP to perform 54 sets of 2-stage simulations for KED and XRF, respectively. The end results are empirical linear functions for the magnitude of the k-edge drop of uranium and plutonium, as well as empirical functions for the XRF peaks for uranium and...
The objective of this thesis work is to utilize computational models to reliably predict the intrins...
Two Hybrid K-edge Densitometers (HKED¿s) recently designed at ITU for different applications are pre...
The original molten salt reactor (MSR) concepts were developed at Oak Ridge National Laboratory (ORN...
The United States is currently looking at options for handling of spent nuclear fuel.Currently, ther...
Pyrochemical reprocessing is a proven method to recover useful fissile material from spent nuclear f...
Hybrid K-edge densitometry (HKED) is a radiometric technique for the non-destructive assay of U and ...
Pyroprocessing is an electrochemical method for recovering actinides from used nuclear fuel and recy...
A mathematical simulation approach based on the general purpose Monte Carlo N-Particle transport cod...
A mathematical simulation approach based on the general purpose Monte Carlo N-Particle transport cod...
A mathematical simulation approach based on the general purpose Monte Carlo N-particle transport cod...
textThe Oak Ridge Isotope Generation and Depletion – Automatic Rapid Proccessing (ORIGEN-ARP) determ...
The quantification of plutonium (Pu) in spent nuclear fuel is an increasingly important safeguards i...
The growing nuclear threat has heightened the need for developing nuclear forensics analysis techniq...
The objective of this project study is to analyze the non-uniformity of used fuel assembly nuclide c...
In the operation of a nuclear power plant, it is very important to determine the time evolution of m...
The objective of this thesis work is to utilize computational models to reliably predict the intrins...
Two Hybrid K-edge Densitometers (HKED¿s) recently designed at ITU for different applications are pre...
The original molten salt reactor (MSR) concepts were developed at Oak Ridge National Laboratory (ORN...
The United States is currently looking at options for handling of spent nuclear fuel.Currently, ther...
Pyrochemical reprocessing is a proven method to recover useful fissile material from spent nuclear f...
Hybrid K-edge densitometry (HKED) is a radiometric technique for the non-destructive assay of U and ...
Pyroprocessing is an electrochemical method for recovering actinides from used nuclear fuel and recy...
A mathematical simulation approach based on the general purpose Monte Carlo N-Particle transport cod...
A mathematical simulation approach based on the general purpose Monte Carlo N-Particle transport cod...
A mathematical simulation approach based on the general purpose Monte Carlo N-particle transport cod...
textThe Oak Ridge Isotope Generation and Depletion – Automatic Rapid Proccessing (ORIGEN-ARP) determ...
The quantification of plutonium (Pu) in spent nuclear fuel is an increasingly important safeguards i...
The growing nuclear threat has heightened the need for developing nuclear forensics analysis techniq...
The objective of this project study is to analyze the non-uniformity of used fuel assembly nuclide c...
In the operation of a nuclear power plant, it is very important to determine the time evolution of m...
The objective of this thesis work is to utilize computational models to reliably predict the intrins...
Two Hybrid K-edge Densitometers (HKED¿s) recently designed at ITU for different applications are pre...
The original molten salt reactor (MSR) concepts were developed at Oak Ridge National Laboratory (ORN...