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論文

Evaluation of fixed absorber reactivity measurement in the prototype fast reactor Monju

大釜 和也; 片桐 寛樹; 竹越 淳*; 羽様 平

Nuclear Technology, 207(12), p.1810 - 1820, 2021/12

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

In the prototype fast breeder reactor Monju, fixed absorber worth was measured as a difference of core reactivity measured by control rod worth between cores with and without a single or three fixed absorbers. In the present paper, the measurements were evaluated in detail and its reliability and usefulness as a validation data were investigated through a comparison with calculations using the latest neutronics design methodology developed in Japan Atomic Energy Agency. Calculated-to-experiment values (C/Es) and their uncertainties of fixed absorber worth were 1.00$$pm$$0.05 and 1.02$$pm$$0.04, respectively. Through this study, the measurements and calculations were found consistent and reliable.

論文

A Validation study of a neutronics design methodology for fast reactors using reaction rate distribution measurements in the prototype fast reactor Monju

大釜 和也; 竹越 淳; 片桐 寛樹*; 羽様 平

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 8 Pages, 2019/05

In the fast breeder reactor prototype Monju, reaction rate distributions were measured by using activation foils during its system startup test. Reliability and usefulness of the measurements as a validation experiment were investigated through a comparison with a calculation using the latest neutronics design methodology developed in JAEA. As a basic calculation, a three-dimensional diffusion calculation with triangular meshes was performed using effective cross sections generated by a one-dimensional heterogeneous lattice model with the JENDL-4.0 nuclear data library. Best-estimate values of reaction rates were evaluated by considering correction factors such as transport correction factors, fine and ultra-fine energy group correction factors, anisotropic diffusion coefficient correction factors and subassembly heterogeneous factors. Through the comparison, it was confirmed that the both of experimental values and analysis results were agreed well in the core region.

論文

原研における二次元ZnS/$$^{6}$$LiFシンチレータ,MSGCガス検出器の開発

中村 龍也; 片桐 政樹; 山岸 秀志; 田中 浩基; 坂佐井 馨; 曽山 和彦

波紋, 15(1), p.67 - 73, 2005/01

本報では原研で開発を進めている高位置分解能二次元ZnS/$$^{6}$$LiFシンチレータ及びMSGCガス検出器に焦点を絞りこれまでの研究開発成果及び今後の展開について述べた。ZnS/$$^{6}$$LiFシンチレータ検出器の開発においては中性子有感シンチレータ/波長シフトファイバ構造の試作検出器により0.6, 0.7mm(各x,y)の位置分解能を有することを確認した。また、ガス検出器開発では独自開発した個別読み出し型検出器システムの動作確認をMWPC素子を用いて行った結果、本システムが位置分解能0.9, 1.4mm(各x,y),良好なn/$$gamma$$弁別能を有することを確認した。

口頭

「もんじゅ」反応率分布測定試験による高速炉核設計手法の妥当性確認

大釜 和也; 竹越 淳; 片桐 寛樹*; 羽様 平

no journal, , 

原型炉「もんじゅ」性能試験データを高速炉核設計手法の妥当性確認用データベースとして整備している。本研究では、放射化箔による反応率分布測定データについて、妥当性確認用データとしての有用性を確認するため、核設計手法による評価結果との比較を行った。

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