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Water activation products generation and transport in DEMO divertor

P. Chiovaro, A. Quartararo, P. Avona, G. Bongiovì, P.A. Di Maio, S. Giambrone, I. Moscato, E. Vallone2024年4月Nuclear FusionIF 3出版社

In water-cooled nuclear reactors, the issue of neutron-activated products transport along the primary heat transfer system (PHTS) is very demanding, as it is a coupled neutronic/fluid-dynamic problem requiring a challenging balance between accuracy and reasonable computational time. This work addresses the transport of water activation products in large hydraulic circuits. Regarding the nuclear calculations, the assessment of the production rates of the radioisotope concentrations has been performed by Monte Carlo analyses adopting the MCNP5.1.6 code, while for the transportation calculations, an innovative method has been expressly developed. It foresees a one-dimensional nodalization, in a MATLAB-Simulink environment, of the hydraulic circuit considered with a computational fluid-dynamic (CFD) characterization (by ANSYS CFX code) of the nodes under neutron flux, that is the components where radioisotopes are formed, and the highest gradients of concentration are present. The method was compared with one-dimensional models not supported by fluid-dynamic analysis. The results of this comparison showed that in cases involving fairly complicated geometries and radioisotopes with a small half-life, CFD analyses are necessary to achieve adequate accuracy. The procedure was applied to very large and rather complex hydraulic circuits like the divertor PHTSs of DEMO fusion reactor to obtain the concentrations of the activation products of the water constituents (16N, 17N, 19O, 14C, 41Ar) along such systems.

日本語訳

水冷原子炉において、一次熱輸送系(PHTS)に沿った中性子活性化生成物の輸送の問題は、精度と妥当な計算時間の間の困難なバランスを必要とする、中性子/流体力学の連成問題であるため、非常に要求が厳しい。本研究は、大型水力回路における水の活性化生成物の輸送を扱う。核計算に関しては、放射性同位体濃度の生成速度の評価は、MCNP5.1.6コードを採用したモンテカルロ解析によって実施された。一方、輸送計算については、独自の革新的な方法が明示的に開発された。この方法は、MATLAB-Simulink環境において、考慮された水力回路の一次元ノード分割を想定し、中性子束下にあるノード、すなわち放射性同位体が生成され、濃度勾配が最も高くなる構成要素に対して、計算流体力学(CFD)特性評価(ANSYS CFXコードによる)を行うものである。この方法は、流体力学解析に裏付けられていない一次元モデルと比較された。この比較の結果、かなり複雑な幾何学形状と短い半減期を持つ放射性同位体を伴う場合には、適切な精度を達成するためにCFD解析が必要であることが示された。この手順は、DEMO核融合炉のダイバータPHTSのような非常に大規模でかなり複雑な水力回路に適用され、そのようなシステムに沿った水の構成成分の活性化生成物(16N、17N、19O、14C、41Ar)の濃度を得た。

wiki

DivertorDEMODEMO divertor

AIによる論文要約

DEMO炉ダイバータにおける水の活性化生成物の生成と輸送
JAこの論文は、核融合炉の設計や安全性評価に携わる研究者や技術者に有用です。冷却水中の放射性物質の挙動を理解し、適切な設計や管理を行うことが重要です。#核融合炉 #ダイバータ #水の活性化 #放射性核種 #CFD

この論文は、核融合炉DEMO炉のダイバータ冷却水中の放射性核種の生成と輸送について研究したものです。複雑な流体力学的な問題を解決するため、CFDを用いた新しい手法を提案しています。この手法により、短半減期の放射性核種の濃度分布を精度良く予測できることが示されました。

Water activation products generation and transport in DEMO divertor
ENThis paper is of interest to fusion researchers and engineers working on the design and safety analysis of nuclear reactor cooling systems, particularly those involving complex geometries and short-lived radioisotopes.#FusionReactor #NuclearSafety #WaterActivation #CFDModeling

This paper addresses the transport of neutron-activated water products in large hydraulic circuits of nuclear reactors. It presents a novel method combining Monte Carlo neutronics analysis and CFD-based fluid dynamics to accurately model the generation and transport of radioisotopes. The method was applied to the DEMO fusion reactor divertor, providing insights into the concentrations of activated water constituents.

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