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

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2022-01-01 DOI:10.1051/epjn/2021025
Heddy Barale, Camille Laguerre, Paul Sabatini, F. Courtin, K. Tirel, G. Martin
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Abstract

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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一个新的工具,模拟不同的核舰队在平衡状态
情景模拟是研究核反应堆机群对相关燃料循环设施影响的主要工具。这项平衡初步研究旨在展示一种新工具的功能,并展示各种各样的反应器/循环/策略,这些反应器/循环/策略可以在稳态条件下进行研究,并通过动态代码进行更详细的验证。多年来,CEA开发了不同类型的情景模拟工具,本研究侧重于动态和平衡代码。动态燃料循环仿真程序模拟了核反应堆机群内所有设施的进出料流及其在一定时间内不同核过程的演变过程。平衡燃料循环模拟代码在平衡条件下模拟先进的核燃料循环,即在稳定选定的核库存(如乏核燃料成分、钚或一些次要锕系元素)的条件下。本工作的原理是分析不同的核反应堆(压水堆,AMR)和几种燃料类型(UOX, MOX, ERU, MIX),以模拟具有部分和完全钚和铀平衡多重回收策略的先进核舰队。在第一阶段,将选择的结果与COSI6模拟进行比较,以评估该新工具的精度,显示出显着的总体一致性。
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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