総合工学 / 原子力学 / 0288Nanashi_et_al.2016/06/07(火) 00:30:21.23 経歴 テキストで表示 1974年4月 京都大学原子炉実験所助手 1990年9月 京都大学原子炉実験所助教授 1996年4月 京都大学原子炉実験所教授 2003年4月 京都大学原子炉実験所長 学歴 テキストで表示 - 1974年 京都大学 工学研究科 原子核工学専攻 - 1969年 京都大学 工学部 原子核工学科 Misc テキストで表示1234> トリウムサイクルと加速器駆動型未臨界炉の炉設計のために必要な研究 原子核研究(1998). 43(1). 27-36 Variance-to-Mean Method Generalized by Linear Difference Filter Technique Ann. Nucl. Energy(1998). 25(9). 639-652 Measurement of Eigenvalue Separation by Using Position Sensitive Proportional Counter Ann. Nucl. Energy(1998). 25(10). 721-732 Time-Spatial Neutron Measurement by Using Position-Sensitive 3He Proportional Counter Nucl. Instr. Meth. in Phys. Res. (1999). A 422(1/3). 64-68 Measurement of Neutron and γ-ray Intensity Distributions with An Optical Fiber-Scintillator Detector Nucl. Instr. Meth. in Phys. Res. (1999). A 422. 129-132 0289Nanashi_et_al.2016/06/07(火) 00:30:38.99 所属学協会
日本原子力学会(839) , 米国原子力学会(17) , 日本加速器学会(118) Works テキストで表示 原子力基礎研究(日本原子力研究所) (動力炉核燃料開発事業団) (原子燃料工業) (堀場製作所) 加速器駆動未臨界炉に関する実験的基礎研究 2000年 - 2002年 競争的資金等の研究課題 テキストで表示 臨界実験による原子炉の核特性研究 臨界実験による核データ・核計算コードの評価 臨界集合体を用いた臨界安全研究 トリウム燃料原子炉、消滅処理用原子炉、研究用原子炉、加速器駆動未臨界炉等の新型原子炉の核設計 新しい原子炉計測法の開発 0290Nanashi_et_al.2016/06/07(火) 00:32:37.46 タイトル: Study on Advanced In-Core Fuel Management for Pressurized Water Reactors Using Loading Pattern Optimization Methods その他のタイトル: 装荷パターン最適化手法を用いたPWR炉心燃料管理の高度化に関する研究 著者: Yamamoto, Akio 著者名の別形: 山本, 章夫 発行日: 23-Mar-1998 出版者: Kyoto University 記述: 本文データは平成22年度国立国会図書館の学位論文(博士)のデジタル化実施により作成された画像ファイルを基にpdf変換したものである 学位授与大学: Kyoto University (京都大学) 学位の種類: 新制・課程博士 取得分野: 博士(エネルギー科学) 報告番号: 甲第7440号 学位記番号: 博第3号 請求記号: 新制/エネ/1 研究科・専攻: 京都大学大学院エネルギー科学研究科エネルギー社会・環境科学専攻 論文調査委員: (主査)教授 神田 啓治, 教授 吉川 榮和, 教授 代谷 誠治 学位授与の要件: 学位規則第4条第1項該当 DOI: 10.11501/3135597 URI: http://hdl.handle.net/2433/156982 出現コレクション: 博士(エネルギー科学) 0291Nanashi_et_al.2016/06/07(火) 00:33:15.10 STUDY ON ADVANCED IN-CORE FUEL MANAGEMENT FOR PRESSURIZED WATER REACTORS USING LOADING PATTERN OPTIMIZATION METHODS AKIO YAMAMOTO Submitted for the Degree of Doctor of Energy Science of KYOTO UNIVERSITY 0292Nanashi_et_al.2016/06/07(火) 00:33:36.73 CONTENTS CHAPTER 1. INTRODUCTION 1.1 Background ---------------------------------------------------------------------------- 1-1 1.2 Basics of in-core fuel management for PWR -------------------------------- 1-2 1.2.1 Description of a PWR core from a viewpoint of in-core fuel management -------------------------------------------- 1-2 1.2.2 Design process of a fuel loading pattern --------------------------- 1-4 1.2.3 Impact of a loading pattern on the core characteristics ------- 1-4 1.2.4 In-core and ex-core fuel managements ----------------------------- 1-6 1.3 Descriptions of the loading pattern optimization problem ------------- 1-7 1. 3.1 Features --------------------------------------------------------------------- 1-7 1.3.2 Objectives and Constraints -------------------------------------------- 1-8 1.3.3 Traditional Approach ---------------------------------------------------- 1-12 1. 3.4 Advanced Approach ------------------------------------------------------ 1-16 1.4 Purpose of this thesis -------------------------------------------------------------- 1-17 1.5 Contents of this thesis ------------------------------------------------------------ 1-19 REFERENCES FOR CHAPTER 1 ------------------------------------------------- 1-22 0293Nanashi_et_al.2016/06/07(火) 00:33:59.62 CHAPTER 2. A QUANTITATIVE COMPARISON OF LOADING PATIERN OPTIMIZATION METHODS FOR IN-CORE FUEL MANAGEMENT OFPWR 2.1 Introduction -------------------------------------------------------------------------- 2-1 2. 2 Optimization Methods ------------------------------------------------------------ 2-3 2. 2.1 Simulated Annealing Method ---------------------------------------- 2-3 2.2.2 Direct Search Method --------------------------------------------------- 2-5 2.2.3 Binary Exchange Method ---------------------------------------------- 2-5 2.2.4 Genetic Algorithms Method ------------------------------------------- 2-6 2.2.5 Hybrid Search Method-------------------------------------------------- 2-8 2. 3 Calculations -------------------------------------------------------------------------- 2-9 2.3.1 Benchmark Problem ---------------------------------------------------- 2-9 2.3.2 Optimization Calculations -------------------------------------------- 2-10 2.3.3 Results and Discussion ------------------------------------------------ 2-12 2. 4 Conclusions -------------------------------------------------------------------------- 2-15 REFERENCES FOR CHAPTER 2 ------------------------------------------------ 2-17 0294Nanashi_et_al.2016/06/07(火) 00:34:25.77 CHAPTER 3. LOADING PATTERN OPTIMIZATION USING HYBRID GENETIC ALGORITHMS 3.1 Introduction ------------------------------------------------------------------------- 3-1 3.2 Optimization Method ------------------------------------------------------------ 3-2 3.2.1 Genetic Algorithms ----------------------------------------------------- 3-2 3.2.2 Application of Genetic Algorithms to Loading pattern Optimization -------------------------------------- 3-3 3.2.3 Development of the GALLOP Code ------------------------------- 3-4 3. 3 Calculations ------------------------------------------------------------------------ 3-5 3.3.1 Single Cycle Optimization Benchmark -------------------------- 3-5 3. 3. 2 Results and Discussion ----------------------------------------------- 3-7 3. 4 Conclusions ------------------------------------------------------------------------- 3-8 REFERENCES FOR CHAPTER 3 ------------------------------------------------ 3-10 0295Nanashi_et_al.2016/06/07(火) 00:35:04.21 CHAPTER 40 INSIGHT: AN INTEGRATED SCOPING ANALYSIS TOOL FOR IN-CORE FUEL MANAGEMENT OF PWR 401 Introduction ------------------------------------------------------------------------ 4-1 402 Software Environment for Developing INSIGHT ---------------------- 4-2 4 0 3 INSIGHT Methodology --------------------------------------------------------- 4-3 40301 System Overview ------------------------------------------------------- 4-3 40302 Loading Pattern Optimization Module(GALLOP) ----------- 4-5 40303 Interactive Loading Pattern Design Module (PATMAK~R) -------------------------------------- 4-7 403.4 Multicycle Analysis Module (MCA) ------------------------------- 4-8 40 30 5 Integrated Database --------------------------------------------------- 4-9 4.4 Applications ------------------------------------------------------------------------ 4-10 4.401 Single Cycle Loading Pattern Optimization ------------------- 4-10 4.402 Multicycle Loading Pattern Optimization ---------------------- 4-12 4 0 5 Conclusions ----------------------------------------------------------------------- 4-14 REFERENCES FOR CHAPTER 4 ----------------------------------------------- 4-16 0296Nanashi_et_al.2016/06/07(火) 00:35:32.09 CHAPTER 50 COMPARISON BETWEEN EQUILIBRIUM CYCLE AND SUCCESSIVE MULTICYCLE OPTIMIZATION METHODS FOR IN-CORE FUEL MANAGEMENT OF PRESSURIZED WATER REACTORS 5.1 Introduction ------------------------------------------------------------------------- 5-1 50 2 Optimization Methods ----------------------------------------------------------- 5-4 5.201 Equilibrium Cycle Optimization Method ------------------------ 5-4 5.2.2 Successive Multicycle Optimization Method ------------------- 5-6 50 3 Calculations ------------------------------------------------------------------------- 5-7 5.3.1 Definitions of Benchmark Problem -------------------------------- 5-7 5.3.2 Optimization Calculations ------------------------------------------- 5-9 5_3.3 Results And Discussions ---------------------------------------------- 5-11 5.4 Conclusions -------------------------------------------------------------------------- 5-15 REFERENCES FOR CHAPTER 5 ------------------------------------------------ 5-18 0297Nanashi_et_al.2016/06/07(火) 00:35:56.77 CHAPTER 6. CONCLUSIONS AND A FUTURE VIEW----------------------- 6-1 ACKNOWLEDGEMENTS 0298Nanashi_et_al.2016/06/07(火) 00:36:56.22 CHAPTER 1 INTRODUCTION 1.1 Background Commercial nuclear reactors haveJ\increasing the i~portance in the role of power generation during past few decades. Actually, the nuclear power accounts for approximately 30% of the Japanese electric power supply, today. Since there is little energy resources in Japan, the nuclear power is considered to be one of the stable and indispensable energy sources. The cost of nuclear power remains lower compared with that of other sources, such as the fossil or hydropower. However, due to improvements in the technology of utilizing the fossil power, especially in an advanced combined cycle (ACC) technology using liquid natural gas (LNG), the superiority of nuclear in the cost of power generation is becoming smaller. To keep the nuclear power competitive, reduction of the power generation cost is desirable. The cost of nuclear power mainly consists of the nuclear fuel cost, the capital cost, the maintenance cost and the replacement power cost during the inspection period. So there are several ways to reduce the cost of nuclear power. In this thesis, improvements of in-core fuel management methods, which can reduce the nuclear fuel cost, will be discussed. Note that the nuclear fuel cost amounts to approximately 20% in the whole nuclear power cost as shown in Table 1-1 (l) ( 2 ). Since the capital cost, which corresponds to the cost of plant construction, is fixed, improvement of the nuclear fuel cost is considered to be one of the important point to reduce the cost of nuclear power generation. 0299Nanashi_et_al.2016/06/07(火) 00:37:23.73 The nuclear fuel cost essentially depends on reactor types, specifications of fuel 1-1 assemblies, the in-core fuel management and reactor operating methods. One of the major tasks of in-core fuel management is to determine a fuel loading pattern. The fuel loading pattern is an arrangement of fuel assemblies in a reactor core, and its design is based on a quite complex combinatorial optimization as will be discussed later in this chapter. Though the loading pattern optimization is one of the primary factors to improve the fuel cycle cost, it was difficult to fmd practical solutions because of its stiff and complicated nature. Therefore, engineers, who are responsible to the in-core fuel management, optimize the loading pattern in every cycle using their state-of-art techniques. Since the optimizations by engineers are mainly based on a trial-and-error approach, a practical limit exists on their optimization capabilities. Recently, high performance computers, such as engineering workstations (EWS) or personal computers (PCs), are being widely used and the calculation cost is rapidly decreasing. Thanks to these powerful computers, practical and robust optimization theories are being developed and being applied for many industrial problems<3 ). 0300Nanashi_et_al.2016/06/07(火) 00:37:50.39 For these backgrounds, this thesis treats optimization problems of the fuel loading pattern and its applications to . the practical in-core fuel management, aiming to reduce the nuclear fuel cost. The target reactor type in this thesis is a pressurized water reactor (PWR), which shares around a half of the commercial reactors in Japan.