第3回モンテカルロシミュレーション研究会報告
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1 JNC (JAPAN ATOMIC ENERGY AGENCY), JAEA) JAEA JAEA 11 p.40 TCA Tanktype Critical Assembly JRR-3Japan Research Reactor-3 JRR-4Japan Research Reactor-4 FCA Fast Critical Assembly JMTR (Japan Materials Testing Reactor) NSRR (Nuclear Safety Research Reactor) STACY (Static Experiment Critical Facility) TRACY (Transient Experiment Critical Facility) HTTRHigh Temperature Engineering Test Reactor Gr Gr Gr Gr Gr Gr JNC Gr JNC Gr JNC -22-
2 Gr FCA FCA FCA Gr -23-
3 4 (1),H14H18 (2) H14H18 (3) Pu H15H19 (4) H17H19 (5) H17H21 (6) MOX H17 (7) (1) Y.Nagaya and T. Mori : "Impact of Perturbed Fission Source on the Effective Multiplication Factor in Monte Carlo Criticality Calculations", J. Nucl. Sci. Technol., Vol.42, No.5, pp (2005). (2) T. Takeda, T. Kitada, I. Kinoshita, T. Matsumura, N. Ueda, M. Yamaoka, S. Okajima: Application of Uncertainty Reduction Factor for Determining Critical Mockup, ICAPP 2005, CD-ROM(2005). (3) Teruhiko KUGO, Kensuke KOJIMA, Masaki Andoh, Shigeaki OKAJIMA, Takamasa MORI,Toshikazu TAKEDA(Osaka Univ.), Takanori KITADA(Osaka Univ.),Shogo MATSUOKA(Osaka Univ.)Preliminary Evaluation of Reduction of Prediction Error in Breeding Light Water Reactor Core Performance, ICAPP 2005, CD-ROM(2005). (4) T. Okubo, S. Uchikawa, T. KUGO, H. Akie, T. Iwamura: Core Concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR), ICAPP 2005, CD-ROM(2005). (5) I. Kinishita, T. Koga, T. Takeda, T. Higuchi, S. Okajima: "Development of An Advanced Controlling System for Non-refueling Reactors", ICAPP 2005, CD-ROM(2005). (6) Haicheng WU, Keisuke OKUMURA and Keiichi SHIBATA, "Proposal of New 235U Nuclear Data to Improve keff Biases on 235U Enrichment and Temperature for Low Enriched Uranium Fueled Lattices Moderated by Light Water," JAERI-Research (2005). (7) T. Iwamura, S. Uchikawa, T. Okubo, T. Kugo, H. Akie and T. Nakatsuka:Concept of Innovative Water Reactor for Flexible Fuel Cycle (FLWR), Proceedings of ICONE13, ICONE , Beijing, China, May 16-20, (2005). (8) T. KUGO, T. MORIBenchmark Solution for Unstructured Geometry PWR Problem by Method of Characteristics using Combinatorial Geometry, M&C2005. (9) Y Nagaya, T. Mori, K. Okumura, and M. Nakagawa, "MVP/GMVP Version 2: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods," JAERI
4 (2005). (10),,, "KRITZ-2," JAERI-Research (2005). (11) Okajima, Fukushima et.al.: Development of Neutronics Analysis Technique for Non-refueling Core (Part 1: Experiment), ANS winter meeting(2005). (12) Sadao Uchikawa, Tsutomu Okubo, Teruhiko Kugo, Hiroshi Akie, Yoshihiro Nakano, Akira Onuki and T. Iwamura :Investigation on Innovative Water Reactor for Flexible Fuel Cycle(FLWR) (1) Conceptual Design, Proceedings of GLOBAL 2005, Paper 358, Tsukuba, Japan, Oct. 9-13, (2005). (13) Tsutomu Okubo, Sadao Uchikawa, Teruhiko Kugo, Hiroshi Akie and Renzo TAKEDA : Investigation on Innovative Water Reactor for Flexible Fuel Cycle(FLWR) (2) Recycle Characteristics, Proceedings of GLOBAL 2005, Paper 359, Tsukuba, Japan, Oct. 9-13, (2005). (14) T. Iwamura, S. Uchikawa, T. Okubo, T. Kugo and H. Akie :Investigation on Innovative Water Reactor for Flexible Fuel Cycle(FLWR), Proceedings of the Second Asian Specialist Meeting on Future Small-Sized LWR Development, Yogyakarta, Indonesia, Nov , (2005). -25-
5 STACY TRACY MOX Gr -26-
6 NUCEF STACYTRACY STACY TRACY MOX -27-
7 Gr Gr ADS J-PARC ADS ADS ADS ADS J-PARC J-PARC ADS Gr -28-
8 ADS ADS MA ADS ADS 550 ADS ADS : 800MWt :270MWe : 1.5GeV30MW : Pb-Bi : Pb-Bi k eff = 0.97 MA : 2.5t : (MA +Pu) + ZrN : -1: Pu/HM=30.0% -2: Pu/HM=48.5% : 10%MA / 600EFPD, 1 1 ADS 11.8m 13.5m J-PARC J-PARC MA ADS 2 FCA 10W 3 MA -29-
9 ADS FBR 2 3 MA Sr-Cs HLW -30-
10 FBR Gr FBR Gr MALLFP FP Gr -31-
11 10% ADJ2000R200 Na (120 kwe) Pu-239 * * MA Minor Actinide: MA MA MA MA Gr MA MA -32-
12 MA Sample Irradiation Positions B9: 3 rd Row, 276 EFPD (29 th -33 rd Cycle) SMIR-26: 5 th Row, 251 EFPD (30 th -33 rd Cycle) MA-loaded position Driver Fuel Control Rod Irradiation Test Assembly Reflector Core Address 3 rd Row (3B2) 5 th Row (5B5) Axial Position Core Midplane 350 mm Upper (in reflector) Core Midplane 350 mm Upper (in reflector) MA Samples (Total number: 16) 237 Np, 241 Am, 243 Am, 244 Cm 237 Np, 241 Am, 243 Am, 244 Cm 237 Np, 241 Am, 243 Am, 244 Cm 237 Np, 241 Am, 243 Am, 244 Cm B9 irradiation test subassembly Mk-II MA
13 FBR FBR FBR (hayashi.hideyuki@jaea.go.jp) FBR 1999 FBR FS FBR (1) Pu Pu -34-
14 Gr Pu Pu BOEC EOEC [W/cc] EOEC [W/cc] BOEC [cm] [cm] Pu (2) FS
15 -36-
16 FBR Gr. MA 10 3 MA MA MA MEISTER FBR Gr. usami.shin@jaea.go.jp -37-
17 Na MA MA,FP MA, FP burn up Max. linear power W/cm Max. linear power W/cm Cycle Length months Cycle Length months Average burn up Average GWd/t burn up GWd/t MA MA FBR 2015 MA 2010 MA MA GIFGeneration International Forum MA Global Actinide Cycle International DemonstrationGACID 16 9 MEISTERMonju Easy-to-Introduce System for Total Evaluation of Reactor Core -38-
18 -39-
19 JAEA ATOMICAhttp://mext-atm.jst.go.jp/atomica/index2.html TCA Tanktype Critical Assembly 200W MOX JRR-3Japan Research Reactor-3 20MW 20 JRR-4Japan Research Reactor-4 3.5MW 20 FCA Fast Critical Assembly 2kW JMTR (Japan Materials Testing Reactor ) 50MW 20 RI() NSRR (Nuclear Safety Research Reactor) 300kMW 23GW
20 140MW MOX 714MW280MW MOX STACY (Static Experiment Critical Facility) 200W TRACY (Transient Experiment Critical Facility) 10kW 5GW HTTRHigh Temperature Engineering Test Reactor 30MW JRR VHTRC1999 DCA2001 (2003 ) -41-
MOX MOX MOX
1 4 2 OECD 130$/kg 400 1 2001 64,000 60 235 0.7 238 235 3 5 235 238 235 2 1 99 99 ( 4.1.1.1) 60 1 2 MOX MOX MOX 238 3 3 (http://www.fepc.or.jp/menu/nuclear/nuclear8.html ) MOX PUREX 4.1.2.1 3 4cm 4 5 6
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29 2004 6 June, 2004 Foreign Professional Societies Coordinating Committee of Atomic Energy Society of Japan and Japan Section of the American Nuclear Society 25 26 25 26 25(2003 ) 1 26 2003 J. J. Lavigne
IEEE HDD RAID MPI MPU/CPU GPGPU GPU cm I m cm /g I I n/ cm 2 s X n/ cm s cm g/cm
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ISSN 0919-4908 Autumn 2008 No.63 1 Plutonium No.63 Autumn 2008,, (NPT) NPT NPT NPT NPT NPT NPT NPT NPT NPT NPT NPT IAEA NPT NPT NPT NPT NPT NPT NPT (IAEA) IAEA IAEANPT (NSG) NSG NSG NGS NPTIAEA NPT NSG
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30 2005 8 August, 2005 Foreign Professional Societies Coordinating Committee of Atomic Energy Society of Japan and Japan Section of the American Nuclear Society 26 27 26 27 26(2004 ) 1 27 2004 ANS The
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Study 6 Watch Experiment & Experience Experiment & Experience 2007 8/21() JAEA 2007 10/3() JAEA JAEA 2007 12/3 () JAEA JAEA 2007 8/28()30() 8/28 NSRR (JAEA) FCA (JAEA) 8/29 JRR-4(JAEA) 8/30 2007 9/10()14()
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Key Words: probabilisic scenario earthquake, active fault data, Great Hanshin earthquake, low frequency-high impact earthquake motion, seismic hazard map 3) Cornell, C. A.: Engineering Seismic
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4 Development of Optical Ground Station System 4-1 Overview of Optical Ground Station with 1.5 m Diameter KUNIMORI Hiroo, TOYOSHMA Morio, and TAKAYAMA Yoshihisa The OICETS experiment, LEO Satellite-Ground
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Japan Atomic Energy Agency, Ibaraki 311-0193, Japan 1) Kyoto University, Uji 611-0011, Japan 2) National Institute of Advanced Industrial Science and Technology, Tsukuba 305-8569, Japan 3) Central Research
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Mover Design and Performance Analysis of Linear Synchronous Reluctance Motor with Multi-flux Barrier Masayuki Sanada, Member, Mitsutoshi Asano, Student Member, Shigeo Morimoto, Member, Yoji Takeda, Member
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