scholarly journals NMB4.0: development of integrated nuclear fuel cycle simulator from the front to back-end

2021 ◽  
Vol 7 ◽  
pp. 19
Author(s):  
Tomohiro Okamura ◽  
Ryota Katano ◽  
Akito Oizumi ◽  
Kenji Nishihara ◽  
Masahiko Nakase ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Material Balance ◽  
Nuclear Fuel Cycle ◽  
Nuclear Material ◽  
Energy Utilization ◽  
Cycle Simulation ◽  
Computational Performance ◽  
Balance Analysis ◽  
Technical Features

Nuclear Material Balance code version 4.0 (NMB4.0) has been developed through collaborative R&D between TokyoTech&JAEA. Conventional nuclear fuel cycle simulation codes mainly analyze actinides and are specialized for front-end mass balance analysis. However, quantitative back-end simulation has recently become necessary for considering R&D strategies and sustainable nuclear energy utilization. Therefore, NMB4.0 was developed to realize the integrated nuclear fuel cycle simulation from front- to back-end. There are three technical features in NMB4.0: 179 nuclides are tracked, more than any other code, throughout the nuclear fuel cycle; the Okamura explicit method is implemented, which contributes to reducing the numerical cost while maintaining the accuracy of depletion calculations on nuclides with a shorter half-life; and flexibility of back-end simulation is achieved. The main objective of this paper is to show the newly developed functions, made for integrated back-end simulation, and verify NMB4.0 through a benchmark study to show the computational performance.

The Nuclear Fuel Services, Inc. Program to Support Disposition of Enriched Uranium-Bearing Materials

2007 ◽  
Author(s):  
Stephen M. Schutt ◽  
Norman P. Jacob
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Nuclear Material ◽  
Nuclear Materials ◽  
Bearing Materials ◽  
Enriched Uranium

The disposition of surplus nuclear materials has become one of the most pressing issues of our time [1, 2]. Numerous agencies have invoked programs with the purpose of removing such materials from various international venues and dispositioning these materials in a manner that achieves non-proliferability. This paper describes the Nuclear Fuel Services, Inc (NFS) Nuclear Material Disposition Program, which to date has focused on a variety of Special Nuclear Material (SNM), in particular uranium of various enrichments. The major components of this program are discussed, with emphasis on recycle and return of material to the nuclear fuel cycle.

Physical model of the nuclear fuel cycle simulation code SITON

2017 ◽  
Vol 99 ◽  
pp. 471-483 ◽  
Author(s):  
Á. Brolly ◽  
M. Halász ◽  
M. Szieberth ◽  
L. Nagy ◽  
S. Fehér
Keyword(s):  
Physical Model ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Simulation Code ◽  
Cycle Simulation

scholarly journals Fundamental concepts in the Cyclus nuclear fuel cycle simulation framework

2016 ◽  
Vol 94 ◽  
pp. 46-59 ◽  
Author(s):  
Kathryn D. Huff ◽  
Matthew J. Gidden ◽  
Robert W. Carlsen ◽  
Robert R. Flanagan ◽  
Meghan B. McGarry ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Simulation Framework ◽  
Cycle Simulation

scholarly journals A VISION of Advanced Nuclear System Cost Uncertainty

2008 ◽  
Author(s):  
J’Tia P. Taylor ◽  
David E. Shropshire ◽  
Jacob J. Jacobson
Keyword(s):  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Department Of Energy ◽  
Oxide Fuel ◽  
Construction Time ◽  
Cost Uncertainty ◽  
Cycle Simulation ◽  
Advanced Fuel ◽  
Mass Flows

VISION (VerifIable fuel cycle SImulatiON) is the Advanced Fuel Cycle Initiative’s nuclear fuel cycle systems code designed to simulate the U.S. commercial reactor fleet. The code is a dynamic stock and flow model that tracks key material mass flows at the elemental and isotopic levels through the entire nuclear fuel cycle. VISION.ECON is a submodel of VISION that was developed to estimate the costs of electricity. The sub-model uses the mass flows generated by VISION for each of the fuel cycle functions and calculates costs based on the Department of Energy Advanced Fuel Cycle Cost Basis report. This paper provides an evaluation of the cost uncertainty effects attributable to fuel cycle system parameters and scheduling variations. A scenario utilizing a single light-water reactor (LWR) using uranium oxide fuel is examined to ascertain the effects of simple parameter changes. The four variable parameters are burnup, thermal efficiency, capacity factor, and reactor construction time. The effect variables are the total cost of electricity (TCOE) and the fuel cycle costs (FCC). Strategies for future analysis are also discussed. Future work consists of extending the analysis to more complex scenarios, including LWRs using mixed oxide fuel and fast recycling reactors using transuranic fuel.

Verifiable Fuel Cycle Simulation Model (VISION): A Tool for Analyzing Nuclear Fuel Cycle Futures

2010 ◽  
Vol 172 (2) ◽  
pp. 157-178 ◽  
Author(s):  
Jacob J. Jacobson ◽  
A. M. Yacout ◽  
Gretchen E. Matthern ◽  
Steven J. Piet ◽  
David E. Shropshire ◽  
...  
Keyword(s):  
Simulation Model ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Cycle Simulation

scholarly journals COSI7: THE NEW CEA REFERENCE ELECTRO-NUCLEAR SIMULATION TOOL

2021 ◽  
Vol 247 ◽  
pp. 13001
Author(s):  
G. Krivtchik
Keyword(s):  
Nuclear Fuel ◽  
User Experience ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Physical Models ◽  
Analysis Tool ◽  
Simulation Code ◽  
New Developments ◽  
Simulation Tools ◽  
Cycle Simulation

Nuclear fuel cycle scenario studies are used as a prospective analysis tool in order to provide stakeholders with decision aid. Nuclear fuel cycle simulation tools model the deployment of reactor fleets, the mass flows in the fuel cycle, and track the nuclear materials. The CEA has been developing for more than 30 years the nuclear fuel cycle tool COSI. The latest version, COSI7, was designed in order to model dynamic systems of ever-increasing complexity with improved user experience. The new developments include functionalities designed to improve the user experience as well as new physical models and post-processing capabilities. COSI7 supersedes COSI6 as the CEA reference nuclear fuel cycle simulation code starting January 2020.

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