Neutronic predictors for PWR fuelled with multi-recycled plutonium and applications with the fuel cycle simulation tool CLASS

2017 ◽  
Vol 100 ◽  
pp. 33-47 ◽  
Author(s):  
Fanny Courtin ◽  
Baptiste Leniau ◽  
Nicolas Thiollière ◽  
Baptiste Mouginot ◽  
Xavier Doligez ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Simulation Tool ◽  
Cycle Simulation

NFCSim: A Dynamic Fuel Burnup and Fuel Cycle Simulation Tool

2005 ◽  
Vol 151 (1) ◽  
pp. 35-50 ◽  
Author(s):  
Erich A. Schneider ◽  
Charles G. Bathke ◽  
Michael R. James
Keyword(s):  
Fuel Cycle ◽  
Fuel Burnup ◽  
Simulation Tool ◽  
Cycle Simulation

Characterizing the United States Nuclear Used Fuel Inventory Using the Cyclus Fuel Cycle Simulator

2016 ◽  
Author(s):  
Cem Bagdatlioglu ◽  
Robert Flanagan ◽  
Erich Schneider
Keyword(s):  
United States ◽  
Reference Data ◽  
Fuel Cycle ◽  
Nuclear Reactors ◽  
The United States ◽  
Energy Information Administration ◽  
Reactor Modeling ◽  
Cycle Simulation ◽  
The Us ◽  
Energy Information

The used fuel inventory of the United States commercial nuclear fleet has been accumulating since the inception of nuclear reactors. In order to understand the mass and composition of the used fuel inventory, a nuclear fuel cycle simulation package (Cyclus) is used with a reactor modeling tool (Bright-lite). The parameters for the simulation are obtained as historical operation and burnup data for every reactor in the US fleet, taken from the U.S. Energy Information Administration. The historical burnup data is used to calculate the fuel enrichment of every reactor at every refueling. Discharged uranium inventories calculated by the software are shown to closely match the reference data. The total mass of three major actinide groups are presented as they build up over time. In addition, the evolution of the plutonium composition in discharged fuel is also presented, illustrating Cyclus’ ability to track the composition of material flowing through a large, evolving reactor fleet over decades.

Neutronic Analysis and Fuel Cycle Simulation of the MIT Reactor Using MCODE-FM and Experimental Validation

2013 ◽  
Author(s):  
Kaichao Sun ◽  
Michael Ames ◽  
Thomas Newton ◽  
Lin-wen Hu
Keyword(s):  
Fuel Cycle ◽  
Search Algorithm ◽  
Reactor Core ◽  
Axial Position ◽  
Monte Carlo Code ◽  
Massachusetts Institute Of Technology ◽  
Fuel Management ◽  
Cycle Simulation ◽  
Start Up ◽  
Institute Of Technology

A neutronic analysis of the Massachusetts Institute of Technology Research Reactor (MITR) is performed using state-of-the-art computational tools: the continuous-energy Monte Carlo code MCNP5 and the point-depletion code ORIGEN2.2. These codes are externally coupled by the in-house code package, MCODE (MCNP-ORIGEN Coupled Depletion Program), more recently, it being extended to MCODE-FM (Fuel Management). The latter features automated input file generation, data manipulation, and post-processing of the output data for the fuel cycle analysis, so that it is used to simulate the fuel management of the MITR. MCODE-FM also has an optional criticality search algorithm to simulate control blade movement. The code validation is carried out by comparing the calculated results to experimental data. Two sets of the comparisons are made in the present paper: 1) the Xe-135 reactivity effect during the reactor start-up and shutdown and 2) the thermal and fast neutron flux in an irradiation capsule in the reactor core. Good agreements have been found. The validated MCODE-FM is therefore useful for neutronic analysis and the fuel cycle simulation of the MITR. The time dependent variation of the key parameters, viz. the control blades’ axial position (maintaining criticality) and the fissile inventory in the fuel, is presented.

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

VEGAS: A Fuel Cycle Simulation and Preconditioner Tool with Restricted Material Balances

2016 ◽  
Vol 193 (3) ◽  
pp. 416-429 ◽  
Author(s):  
E. A. Schneider ◽  
U. B. Phathanapirom
Keyword(s):  
Fuel Cycle ◽  
Cycle Simulation

The Potential of Different Concepts of Fast Breeder Reactor for the French Fleet Renewal

2006 ◽  
Author(s):  
Simone Massara ◽  
Philippe Tetart ◽  
David Lecarpentier ◽  
Claude Garzenne ◽  
Alexandre Mourogov
Keyword(s):  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Breeder Reactor ◽  
Simulation Code ◽  
Cycle Simulation ◽  
Waste Production ◽  
Highly Sensitive ◽  
Xxist Century ◽  
Transition Scenario

The performances of different concepts of Fast Breeder Reactor (Na-cooled, He-cooled and Pb-cooled FBR) for the current French fleet renewal are analyzed in the framework of a transition scenario to a 100% FBR fleet at the end of the XXIst century. Firstly, the modeling of these three FBR types by means of a semi-analytical approach in TIRELIRE - STRATEGIE, the EDF fuel cycle simulation code, is presented, together with some validation elements against ERANOS, the French reference code system for neutronic FBR analysis (CEA). Afterwards, performances comparisons are made in terms of maximum deployable power, natural uranium consumption and waste production. The results show that the FBR maximum deployable capacity, independently from the FBR technology, is highly sensitive to the fuel cycle options, like the spent nuclear fuel cooling time or the Minor Actinides management strategy. Thus, some of the key parameters defining the dynamic of FBR deployment are highlighted, to inform the orientation of R&D in the development and optimization of these systems.

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.

scholarly journals A new tool for the simulation of different nuclear fleets at equilibrium

2022 ◽  
Vol 8 ◽  
pp. 1
Author(s):  
Heddy Barale ◽  
Camille Laguerre ◽  
Paul Sabatini ◽  
Fanny Courtin ◽  
Kévin Tirel ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Reactor ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Main Tool ◽  
Simulation Code ◽  
Simulation Tools ◽  
Fuel Cycles ◽  
Cycle Simulation ◽  
The Impact

Scenario simulations are the main tool for studying the impact of a nuclear reactor fleet on the related fuel cycle facilities. This equilibrium preliminary study aims to present the functionalities of a new tool and to show the wide variety of reactors/cycles/strategies that can be studied in steady state conditions and validated with more details thanks to dynamic code. Different types of scenario simulation tools have been developed at CEA over the years, this study focuses on dynamic and equilibrium codes. Dynamic fuel cycle simulation code models the ingoing and outgoing material flow in all the facilities of a nuclear reactor fleet and their evolutions through the different nuclear processes over a given period of time. Equilibrium fuel cycle simulation code models advanced nuclear fuel cycles in equilibrium conditions, i.e. in conditions which stabilize selected nuclear inventories such as spent nuclear fuel constituents, plutonium or some minor actinides. The principle of this work is to analyze different nuclear reactors (PWR, AMR) and several fuel types (UOX, MOX, ERU, MIX) to simulate advanced nuclear fleet with partial and fully plutonium and uranium multi-recycling strategies at equilibrium. At this first stage, selected results are compared with COSI6 simulations in order to evaluate the precision of this new tool, showing a significant general agreement.

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