scholarly journals Theory Manual for the Fuel Cycle Analysis Code REBUS

2020 ◽  
Author(s):  
Won Yang ◽  
Micheal Smith
Keyword(s):  
Fuel Cycle ◽  
Fuel Cycle Analysis

Comparative Fuel Cycle Analysis of Critical and Subcritical Fast Reactor Transmutation Systems

2003 ◽  
Vol 144 (1) ◽  
pp. 83-106 ◽  
Author(s):  
Edward A. Hoffman ◽  
Weston M. Stacey
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Fuel Cycle Analysis

Fuel cycle analysis of TRU or MA burner fast reactors with variable conversion ratio using a new algorithm at equilibrium

2009 ◽  
Vol 239 (10) ◽  
pp. 2160-2168 ◽  
Author(s):  
Massimo Salvatores ◽  
Christine Chabert ◽  
Concetta Fazio ◽  
Robert Hill ◽  
Yannick Peneliau ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Conversion Ratio ◽  
Fast Reactors ◽  
Fuel Cycle Analysis

Generalized Continuous Slowing Down Integral Transport Theory for Fast Reactor Fuel Cycle Analysis

1981 ◽  
Vol 79 (1) ◽  
pp. 124-140
Author(s):  
Ahmed Badruzzaman ◽  
James Biffer ◽  
Tahmina Badruzzaman ◽  
Martin Becker
Keyword(s):  
Fast Reactor ◽  
Transport Theory ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Slowing Down ◽  
Fuel Cycle Analysis ◽  
Fast Reactor Fuel ◽  
Integral Transport

Fuel Cycle Analysis of the SABR Subcritical Transmutation Reactor Concept

2010 ◽  
Vol 172 (1) ◽  
pp. 48-59 ◽  
Author(s):  
C. M. Sommer ◽  
W. M. Stacey ◽  
B. Petrovic
Keyword(s):  
Fuel Cycle ◽  
Fuel Cycle Analysis

scholarly journals Thoria-Based Cermet Nuclear Fuel: Neutronics Fuel Design and Fuel Cycle Analysis

2002 ◽  
Author(s):  
Thomas J. Downar ◽  
Sean M. McDeavitt ◽  
S. T. Revankar ◽  
A. A. Solomon ◽  
T. K. Kim
Keyword(s):  
Nuclear Fuel ◽  
Metal Matrix ◽  
Fuel Cycle ◽  
Performance Model ◽  
Fuel Cycles ◽  
Fuel Cycle Analysis ◽  
Research Initiative ◽  
Fuel Design ◽  
Water Reactors ◽  
Analysis Of Dispersion

Cermet nuclear fuels have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle provide intriguing options for using thoria based cermet nuclear fuel in advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. The following paper will first describe the fuel thermal performance model developed for the analysis of dispersion metal matrix fuels. The model will then be applied to the design and analysis of thorium/uranium/zirconium metal matrix fuel pins for light water reactors using neutronic simulation methods.

scholarly journals Sustainability Features of Nuclear Fuel Cycle Options

2012 ◽  
Vol 4 (10) ◽  
pp. 2377-2398 ◽  
Author(s):  
Stefano Passerini ◽  
Mujid Kazimi
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Energy System ◽  
Nuclear Fuel Cycle ◽  
The United States ◽  
Base Line ◽  
Energy Potential ◽  
Fuel Cycle Analysis ◽  
The Impact

The nuclear fuel cycle is the series of stages that nuclear fuel materials go through in a cradle to grave framework. The Once Through Cycle (OTC) is the current fuel cycle implemented in the United States; in which an appropriate form of the fuel is irradiated through a nuclear reactor only once before it is disposed of as waste. The discharged fuel contains materials that can be suitable for use as fuel. Thus, different types of fuel recycling technologies may be introduced in order to more fully utilize the energy potential of the fuel, or reduce the environmental impacts and proliferation concerns about the discarded fuel materials. Nuclear fuel cycle systems analysis is applied in this paper to attain a better understanding of the strengths and weaknesses of fuel cycle alternatives. Through the use of the nuclear fuel cycle analysis code CAFCA (Code for Advanced Fuel Cycle Analysis), the impact of a number of recycling technologies and the associated fuel cycle options is explored in the context of the U.S. energy scenario over 100 years. Particular focus is given to the quantification of Uranium utilization, the amount of Transuranic Material (TRU) generated and the economics of the different options compared to the base-line case, the OTC option. It is concluded that LWRs and the OTC are likely to dominate the nuclear energy supply system for the period considered due to limitations on availability of TRU to initiate recycling technologies. While the introduction of U-235 initiated fast reactors can accelerate their penetration of the nuclear energy system, their higher capital cost may lead to continued preference for the LWR-OTC cycle.

The Fuel Cycle Analysis System, REBUS

1971 ◽  
Vol 45 (1) ◽  
pp. 52-65 ◽  
Author(s):  
J. Hoover ◽  
G. K. Leaf ◽  
D. A. Meneley ◽  
P. M. Walker
Keyword(s):  
Fuel Cycle ◽  
Fuel Cycle Analysis ◽  
Analysis System
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