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論文

Interaction between caesium iodide particles and gaseous boric acid in a flowing system through a thermal gradient tube (1030 K-450 K) and analysis with ASTEC/SOPHAEROS

Gou$"e$llo, M.*; Hokkinen, M.*; 鈴木 恵理子; 堀口 直樹; Barrachin, M.*; Cousin, F.*

Progress in Nuclear Energy, 138, p.103818_1 - 103818_10, 2021/08

 被引用回数:0 パーセンタイル:0.01(Nuclear Science & Technology)

1023Kから453Kの温度勾配管中のヨウ化セシウム粒子の移行挙動に関するデータを取得した。まず、アルゴン(Ar)と水蒸気(H$$_{2}$$O)で構成される層流条件下にてヨウ化セシウム粒子を温度勾配管中に流し、沈着量を調べた結果、低流速、高蒸気濃度であるほどより多くの粒子が沈着することが分かった。次に、雰囲気の異なる三種類の混合ガス(Ar/H$$_{2}$$O, Ar/H$$_{2}$$, Ar/Air)を流すことで沈着した粒子の再蒸発および/または再浮遊の有無を調べた結果、Ar/H$$_{2}$$OとAr/H$$_{2}$$条件では沈着したものと同等の粒径の粒子が再浮遊する一方で、Ar/Air条件ではより大きな粒子が再浮遊することが分かった。実験結果をASTECコードのSOPHAEROSモジュールを用いて解析した結果、沈着挙動は解析結果と一致するものの、再浮遊挙動は再現できなかった。

論文

Phenomena identification ranking tables for accident tolerant fuel designs applicable to severe accident conditions

Khatib-Rahbar, M.*; Barrachin, M.*; Denning, R.*; Gabor, J.*; Gauntt, R.*; Herranz, L. E.*; Hobbins, R.*; Jacquemain, D.*; 丸山 結; Metcalf, J.*; et al.

NUREG/CR-7282, ERI/NRC 21-204 (Internet), 160 Pages, 2021/04

The U.S. Nuclear Regulatory Commission (NRC) is preparing to accept anticipated licensing applications for the commercial use of accident tolerant fuel (ATF) in commercial nuclear power plants in the United States. It is the objective of the NRC to evaluate the effects of ATF designs on severe accident behavior, and to determine potential changes to the NRC severe accident analysis computer codes that would simulate plant conditions using ATFs commensurate with the accuracy in accident analyses involving conventional fuels. This report documents the development of Phenomena Identification and Ranking Tables (PIRTs) for near-term ATFs under severe accident conditions in light water reactors (LWRs). The PIRTs were developed by a panel of experts for various near-term ATF design concepts (i.e., FeCrAl cladding, zirconium alloy cladding coated with chromium, and Cr$$_{2}$$O$$_{3}$$ dopants in uranium dioxide fuels) in addition to the impacts from fuel enrichment and burnup. Panel members also considered the severe accident implications of the longer-term ATF concepts. The main figures-of-merit considered in this ranking process are the amount of fission products released into the containment and the quantity of combustible gases generated during an accident. Special focus is given to whether existing severe accident codes and models would be sufficient as applied to LWRs employing these fuels, and whether additional experimental studies or model development would be warranted.

論文

Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project

仲吉 彬; Rempe, J. L.*; Barrachin, M.*; Bottomley, D.; Jacquemain, D.*; Journeau, C.*; Krasnov, V.; Lind, T.*; Lee, R.*; Marksberry, D.*; et al.

Nuclear Engineering and Design, 369, p.110857_1 - 110857_15, 2020/12

 被引用回数:0 パーセンタイル:0.33(Nuclear Science & Technology)

福島第一原子力発電所(1F)の各ユニットの燃料デブリの最終状態位置については、まだ多くは不明である。不確実性の低減に向けた最初のステップとして、OECD/NEAは、燃料デブリ分析予備的考察(PreADES)プロジェクトが立ち上げた。PreADESプロジェクトのタスク1の一環として、関連情報をレビューし、燃料デブリの状態の推定図の正確さを確認した。これは、将来の燃料デブリの分析を提案するための基礎となる。具体的にタスク1では2つのアクティビティを実施した。第一に、1Fでの廃止措置活動に資するTMI-2とチェルノブイリ原子力発電所4号機での重大事故の関連知識、プロトタイプ試験とホットセル試験の結果の知見を収集した。第二に、プラント情報とBSAFプロジェクトのシビアアクシデントコード分析からの関連知識が組み込まれている1F燃料デブリの原子炉内の状態に関する現状の推定図を見直した。この報告は、PreADESプロジェクトのタスク1の洞察に焦点を当て、1Fの将来の除染および廃止措置活動に情報を提供するだけでなく、シビアアクシデント研究、特にシビアアクシデントにより損傷した原子力サイトの長期管理に関する重要な視点を提供する。

論文

Advances in fuel chemistry during a severe accident; Update after Fukushima Daiichi Nuclear Power Station (FDNPS) accident

倉田 正輝; 逢坂 正彦; Jacquemain, D.*; Barrachin, M.*; Haste, T.*

Advances in Nuclear Fuel Chemistry, p.555 - 625, 2020/00

福島第一原子力発電所(FDNPS)事故後、燃料化学の重要性が再認識された。運転員による最大限の事故防止・拡大防止の試みもあり、3つのユニットの事故進展の間に大きな違いがあることが福島第一原子力発電所の調査及び解析により明らかになった。燃料デブリの特性はこの事故進展の違いに大きく影響されると考えられ、TMI-2事故の解析と模擬実験に基づく典型的事故シナリオから予想されるものとは異なる。非典型的条件含め、シビアアクシデント(SA)に対する知見を適切に改良するため、燃料・炉心溶融崩落と核分裂生成物(FP)挙動の現象論の改良が必須であり、燃料化学の進展は最も根源的なアプローチとなる。本レビューはFDNPS事故後の最近のアップデートと残された課題に焦点を当てた。

論文

Current situation of OECD/NEA, Preparatory Study on Analysis of Fuel debris (PreADES) project

仲吉 彬; Journeau, C.*; Rempe, J.*; Barrachin, M.*; Bottomley, D.; Nauchi, Y.*; Song, J. H.*

Proceedings of 2019 International Workshop on Post-Fukushima Challenges on Severe Accident Mitigation and Research Collaboration (SAMRC 2019) (USB Flash Drive), 6 Pages, 2019/11

In recognition of the broad international interest in learning from post-accident examinations and other activities related to the Fukushima Daiichi Nuclear Power Station (1F), Japan recommended, to the Organization for Economic Co-operation and Development/Nuclear energy Agency/Committee on Safety of Nuclear Installations (OECD/NEA/CSNI) in 2013, that they identified and followed up on opportunities to address safety research gaps. The CSNI set up the Senior Expert Group (SEG) on Safety Research Opportunities Post-Fukushima (SAREF). In 2016-2017, Preparatory Study on Analysis of Fuel Debris (PreADES) project was recommended by the SEG on SAREF as a near-term project. The PreADES project will summarize the collected knowledge and expertise of debris characterization and identify the needs for debris analyses that will most contribute to the decommissioning of 1F. The project also aims to improve the understanding of severe accidents and reactor safety assessments as well as creating appropriate and optimal methodologies for future debris sampling, retrieval, and storage. Consequently, the project provides important input for a future international project of sample examination based on long-term considerations. The PreADES project launched discussions among interested organizations at the preliminary meeting in July 2017 about the objectives, scope, output, and direction of the project. The contents of the PreADES project were agreed as the three following tasks: Task 1: Joint study on fuel debris' expected properties and characterization, Task 2: Identifying needs and major issues for future fuel debris sampling, retrieval, and analyses, Task 3: Planning of future international R&D framework. Currently, 4th meeting took place on July in Tokyo Japan. Task 1 is almost completed and Task 2 will be summarized soon.

論文

Modelling of cesium chemisorption under nuclear power plant severe accident conditions

Miradji, F.; 鈴木 知史; 西岡 俊一郎; 鈴木 恵理子; 中島 邦久; 逢坂 正彦; Barrachin, M.*; Do, T. M. D.*; 村上 健太*; 鈴木 雅秀*

Proceedings of 9th Conference on Severe Accident Research (ERMSAR 2019) (Internet), 21 Pages, 2019/03

Under the scope of analyses of Fukushima Daiichi Nuclear Power Station (1F) Severe Accident (SA), estimation of Cs distribution, especially localization in the upper part of the core, has large uncertainties partly caused by the current implemented Cs-chemisorption models in SA analysis codes. This is in part due to the scarce knowledge related to Cs chemisorption mechanisms onto structure surfaces. The objective of this work is, therefore, to improve Cs chemisorption models by consolidation and extension of knowledge in the chemical process of Cs chemisorption. In this study, we will present in the first part experimental tests for grasping the phenomenology of Cs chemisorption onto stainless steel (SS) surfaces under reproductive conditions of 1F SA. The chemical factors involving in the Cs chemisorption process were investigated and implemented in an improved Cs chemisorption model based on a mass transfer theory. The second part of the study will discuss further improvement of built Cs chemisorption model to take into account revaporizaton process of Cs chemisorbed species. For such improvement, the thermodynamic properties of all possible Cs-(Fe)-Si-O chemisorbed species were provided using first-principles calculations. In the last part of the study, chemical equilibrium calculations were conducted to evaluate the relative stability of possible Cs-(Fe)-Si-O chemisorbed species in SA conditions.

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