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JAEA-Conf JAEA-Conf 2011-003 日本原子力研究開発機構 Proceedings of the 4th International Symposium on Material Testing Reactors December 5-9, 2011, Oarai, Japan March 2012 Japan Atomic Energy Agency (Eds.) Masahiro ISHIHARA and Masahide SUZUKI Neutron Irradiation and Testing Reactor Center Oarai Research and Development Center

JAEA-Conf 2011-003

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  • JAEA

    -Conf

    JAEA-Conf

    2011-003

    Proceedings of the 4th International Symposium on

    Material Testing Reactors

    December 5-9, 2011, Oarai, Japan

    March 2012

    Japan Atomic Energy Agency

    (Eds.) Masahiro ISHIHARA and Masahide SUZUKI

    Neutron Irradiation and Testing Reactor CenterOarai Research and Development Center

  • JAEA-Conf 2011-003

    Proceedings of the 4th International Symposium on Material Testing Reactors December 5-9, 2011, Oarai, Japan

    (Eds.) Masahiro ISHIHARA and Masahide SUZUKI

    Neutron Irradiation and Testing Reactor Center

    Oarai Research and Development Center Japan Atomic Energy Agency

    Oarai-machi, Higashiibaraki-gun, Ibaraki-ken

    (Received December 21, 2011)

    This report is the Proceedings of the fourth International Symposium on Material Testing Reactors hosted by

    Japan Atomic Energy Agency (JAEA). The first symposium was held on 2008, at the Oarai Research and Development Center of JAEA, the second, 2009, Idaho National Laboratory (INL) of United States and the third 2010, Nuclear Research Institute (NRI) in Czech Republic to exchange information for deep mutual understanding of material testing reactors. The fourth symposium was originally scheduled to be held INVAP in Argentina. However, the aftermath of volcanic explosion at Chili forced the symposium to change place. Total 111 participants attended from Argentina, Belgium, France, Germany, Indonesia, Malasia, Korea, South Africa, Switzerland, the United State and Japan.

    This symposium addressed the general topics of status and future plan of material testing reactors, advancement of irradiation technology, expansion of industry use(RI), facility, upgrade, aging management, new generation MTR, advancement of PIE technology, development of advanced driver fuel, and nuclear human resource development(HRD) for next generation, and 39 presentations were made. Furthermore, three topics, Necessity of cooperation for Mo-99 production by (n,gamma) reaction, Necessity of standardization of irradiation technology and Conceptual design of next generation materials testing reactor by collaboration, were selected and discussed.

    Keywords : Material Testing Reactors, International Symposium, Status and Future Plan of MTR, Material Development, Irradiation Technology, PIE, Utilization, World Network, Management on Re-operation

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  • JAEA-Conf 2011-003

    iii

    Contents

    1. Introduction 1 2. Circumstances surrounding RR's in the World 5

    2.1 Research with Neutrons in Germany in View of the Phase Out of Nuclear Power 7 J.Knebel, W.Petry

    2.2 Nuclear Research Policy in the Evolving Political Context of Switzerland 27 J.Cavedon, J.Dreier, P.Hardegger

    2.3 Advancing Nuclear Technology and Research: The Advanced Test Reactor National Scientific User Facility 37

    J.B.Benson, T.R.Allen, F.M.Marshall 3. Status, Future Plans 45

    3.1 RSG-GAS: Current and Strategic Plan of Future Activities 47 A.R. Antariksawan, A.Tarigan

    3.2 The University of Missouri Research Reactor HEU to LEU Conversion Project Status 55 J.C.McKibben, K.Kutikkad, L.P.Foyto, N.J.Peters, G.L.Solbrekken, J.Kennedy, J.A.Stillman, E.E.Feldman, C.P.Tzanos, J.G.Stevens

    3.3 SAFARI-1 Research Reactor Beryllium Reflector Element Replacement, Management and Relocation 65 M.De Kock, JWH Vlok, BJ Steynberg

    3.4 Material Test Reactor Fuel Research at the BR2 Reactor 75 S.Van Dyck, E.Koonen, S.Van den Berghe

    3.5 Review on the Seismic Safety of JRR-3 according to the Revised Regulatory Code on Seismic Design for Nuclear Reactors 83

    T.Kobayashi, M.Araki, T.Ohba, Y.Torii, M.Takeuchi 3.6 Present Status of Japan Materilas Testing Reactor 87

    N.Hori, M. Kaminaga, T. Kusunoki, M. Ishihara, M.Niimi, Y. Komori, M. Suzuki, H.Kawamura 4. Advancement of Irradiation Technology (1) 91

    4.1 Status of Material Development for Lifetime Expansion of Beryllium Reflector 93 C.Dorn, K.Tsuchiya, Y.Hatano, P.Chakrov, M.Kodama, H.Kawamura

    4.2 Beryllium Reflectors for Research Reactors. Review and Preliminary Finite Element Analysis 99 P.S.Bejarano, R.G.Cocco

    4.3 Irradiation Tests of Nuclear Grade Graphite at High Neutron Dose and Low Temperature at HANARO 107

    D.Kim, S.H.Kang, H.H.Jin, B.G.Kim, M.H.Choi, T.K.Kim, Y.H.Jeong

  • JAEA-Conf 2011-003

    iv

    5. Advancement of Irradiation Technology (2) 115 5.1 In-pile IASCC Growth Tests of Irradiated Stainless Steels in JMTR 117

    Y.Chimi, S.Kasahara, A.Shibata, H.Ise, Y.Kawaguchi, J.Nakano, M.Ohmi, Y.Nishiyama 5.2 Design Modification of the In-Pile Test Section for Increase of Sealing Capability 123

    J.T. Hong, S.H. Ahn, C.Y. Joung, H.Y. Jeong, J.M.Lee, B.S.Sim 5.3 Status for Development of a Capsule and Instruments for

    High-Temperature Irradiation in HANARO 129 M.S.Cho, K.N.Choo, C.Y.Lee, S.W.Yang, K.T.Shim, H.S.Chung

    6. Expansion of Industry Use (RI) 135

    6.1 Status of 99Mo-99mTc Production Development by (n,) Reaction 137 K.Tsuchiya, A.Mutalib, P.Chakrov, M.Kaminaga, M.Ishihara, H.Kawamura

    6.2 Development of Mo Recycle Technique from Generator Materials 143 M.Tanimoto, S.Kakei, M.Kurosawa, A.Kimura, K.Nishikata, H.Yoshinaga, K.Tsuchiya

    6.3 Development of 99mTc Extraction-recovery by Solvent Extraction Method 147 A.Kimura, K.Nishikata, M.Tanase, S.Fujisaki, H.Izumo, K.Tsuchiya, T.Shiina, A.Ohta, N.Takeuchi, M.Ishihara

    7. Facility, Upgrade, Aging Management 151

    7.1 MIT Research Reactor Power Uprate and Utilization 153 L.W.Hu

    7.2 Overview of Refurbishment Project of JMTR 157 H.Izumo, N.Hori, M.Kaminaga, T.Kusunoki, M.Ishihara,Y.Komori, M.Suzuki, H.Kawamura

    7.3 Real-time Personal Exposure and Health Condition Monitoring System 163 I.Saitou, H.Kanda, A.Asai, N.Tateishi,Y.Ota, N.Hanawa, H.Ueda, T.Kusunoki, E.Ishitsuka, H.Kawamura

    7.4 OPAL Shield Design Performance Assessment: Comparison of Measured Dose Rates Against the Corresponding Design Calculated Values A Designer Perspective 165

    M.Brizuela, F. Albornoz 7.5 OPAL Reactor Calculations using the Monte Carlo Code Serpent 171

    D.Ferraro, E.Villarino 8. Advancement of Irradiation Technology (3) 177

    8.1 Irradiation Creep and Growth Behavior of Zircaloy-4 Inner Shell of HANARO 179 J.H.Chung, Y.G.Cho, J.I.Kim

    8.2 Development of In-pile Instruments for Fuel and Material Irradiation Tests 185 A.Shibata, S.Kitagishi, N.Kimura, T.Saito, J.Nakamura, M.Ohmi, H.Izumo, K.Tsuchiya

    8.3 Thermal Analysis on the Specimens for Low Irradiation Temperature below 100oC in the HANARO 189 M.H.Choi, B.G.Kim, B.C.Lee, T.K.Kim

    8.4 Development of Reactor Water Level Sensor for Extreme Conditions 193 K.Miura, A.Shibata, J.Nakamura, T.Ogasawara, T.Saito, K.Tsuchiya

  • JAEA-Conf 2011-003

    v

    9. New Generation MTR 197 9.1 INVAP Nuclear Energy Division Main Activities 2011 199

    R.Mazzi 9.2 MYRRHA

    An Innovative and Unique Research Facility 207 R.Fernandez, B.Neerdael, M.Schyns, S.V.Dyck, S.Michiels, H.A.Abderrahim

    9.3 Conceptual Design of Next Generation MTR 217 H.Nagata, T.Yamaura, M.Naka, K.Kawamata, H.Izumo, N.Hori,Y.Nagao, T.Kusunoki, M.Kaminaga, Y.Komori, M.Suzuki, M.Mine,S.Yamazaki, S.Ishikawa, K.Miura, S.Nakashima, K.Yamaguchi, H.Kawamura

    10. Advancement of PIE Technology 223

    10.1 Development of Fracture Toughness Estimation Method using Thin Tube 225 M.Sugiyama, T.Torimaru, K.Chatani

    10.2 Improvement of the Center Boring Device for the Irradiated Fuel Pellets 231 K.Usami, A.Onozawa, Y.Kimura, N.Sakuraba, H.Shiina, A.Harada, M.Nakata

    10.3 Development of High Resolution X-Ray CT Technique for Irradiated Fuel Assembly 235 A.Ishimi, K.Katsuyama, K.Maeda, T.Asaga

    11. Development of Advanced Driver Fuel 239

    11.1 CERCA Industrial Approach to Customers Needs 241 Dominique GESLIN

    11.2 Development of U-Mo/Al Dispersion Fuel for Research Reactors 249 J.M.Park, H.J.Ryu, J.H.Yang, Y.J.Jeong, Y.S.Lee

    12. Nuclear HRD for Next Generation, Other 255

    12.1 Activity of the Nuclear Human Resource Development Center in Japan Atomic Energy Agency 257 K.Yamashita, H.Murakami, N.Nakagawa, N.Arai, K.Matsuura, Y.Ohzeki

    12.2 Training Program for Students and Young Engineers in JMTR 265 N.Takemoto, H.Izumo, N.Hori, E.Ishitsuka, M.Suzuki

    12.3 Real Time Simulator for Material Testing Reactor 271 N.Takemoto, T.Imaizumi, H.Izumo, N.Hori, M.Suzuki, T.Ishitsuka, K.Tamura

    12.4 Report of the 1st Asian Symposium on Materials Testing Reactor 277 H.Kawamura, E.Ishitsuka, Mohd Fairus Abdul Farid, Julia Abdul Karim, H.Izumo, Mohamad Puad Abu, Muhd Noor Muhd Yunus, Mohd Ashhar Hj Khalid

    13. Summary 283

    Appendix Symposium Program 293

  • JAEA-Conf 2011-003

    vi

    1. 1

    2. 5

    2.1 7

    J.Knebel, W.Petry

    2.2 27

    J.Cavedon, J.Dreier, P.Hardegger

    2.3 : ATR 37

    J.B.Benson, T.R.Allen, F.M.Marshall

    3. 45

    3.1 RSG-GAS: 47

    A.R. Antariksawan, A.Tarigan

    3.2 HEU LEU 55

    J.C.McKibben, K.Kutikkad, L.P.Foyto, N.J.Peters, G.L.Solbrekken,

    J.Kennedy, J.A.Stillman, E.E.Feldman, C.P.Tzanos, J.G.Stevens

    3.3 SAFARI-1 65

    M.De Kock, JWH Vlok, BJ Steynberg

    3.4 BR2 75

    S.Van Dyck, E.Koonen, S.Van den Berghe

    3.5 JRR-3 83

    T.Kobayashi, M.Araki, T.Ohba, Y.Torii, M.Takeuchi

    3.6 (JMTR) 87

    N.Hori, M. Kaminaga, T. Kusunoki, M. Ishihara,

    M.Niimi, Y. Komori, M. Suzuki, H.Kawamura

    4. (1) 91

    4.1 93

    C.Dorn, K.Tsuchiya, Y.Hatano, P.Chakrov, M.Kodama, H.Kawamura

    4.2 99

    P.S.Bejarano, R.G.Cocco

    4.3 HANARO 107

    D.Kim, S.H.Kang, H.H.Jin, B.G.Kim, M.H.Choi, T.K.Kim, Y.H.Jeong

  • JAEA-Conf 2011-003

    vii

    5. (2) 115

    5.1 JMTRIASCC 117

    Y.Chimi, S.Kasahara, A.Shibata, H.Ise,Y.Kawaguchi, J.Nakano, M.Ohmi, Y.Nishiyama

    5.2 123

    J.T. Hong, S.H. Ahn, C.Y. Joung, H.Y. Jeong, J.M. Lee, B.S. Sim

    5.3 HANARO 129

    M.S.Cho, K.N.Choo, C.Y.Lee, S.W.Yang, K.T.Shim, H.S.chung

    6. (RI) 135

    6.1 (n,)99Mo-99mTc 137

    K.Tsuchiya, A.Mutalib, P.Chakrov, M.Kaminaga, M.Ishihara, H.Kawamura

    6.2 99Mo 143

    M.Tanimoto, S.Kakei, M.Kurosawa, A.Kimura,

    K.Nishikata, H.Yoshinaga, K.Tsuchiya

    6.3 99mTc 147

    A.Kimura, K.Nishikata, M.Tanase, S.Fujisaki, H.Izumo,

    K.Tsuchiya, T.Shiina, A.Ohta, N.Takeuchi, M.Ishihara

    7. , , 151

    7.1 MIT 153

    L.W.Hu

    7.2 JMTR 157

    H.Izumo, N.Hori, M.Kaminaga, T.Kusunoki,M.Ishihara,Y.Komori, M.Suzuki, H.Kawamura

    7.3 163

    I.Saitou, H.Kanda, A.Asai, N.Tateishi, Y.Ota,N.Hanawa, H.Ueda, T.Kusunoki, E.Ishitsuka,

    H.Kawamura

    7.4 OPAL:

    - - 165

    M.Brizuela, F.Albornoz

    7.5 SerpentOPAL 171

    D.Ferraro, E.Villarino

    8. (3) 177

    8.1 HANARO-4 179

    Jong-Ha Chung, Yeong-Garp Cho, Jong-In Kim

    8.2 185

    A.Shibata, S.Kitagishi, N.Kimura, T.Saito,

    J.Nakamura, M.Ohmi, H.Izumo, K.Tsuchiya

    8.3 HANARO100 189

    Myoung-Hwan Choi, Bong-Goo Kim, Byung-Chul Lee, Tae-Kyu Kim

    8.4 193

    K.Miura, A.Shibata, J.Nakamura, T.Ogasawara, T.Saito, K.Tsuchiya

  • JAEA-Conf 2011-003

    viii

    9. 197

    9.1 INVAP 2011 199

    R. Mazzi

    9.2 MYRRHA -- 207

    R.Fernandez, B.Neerdael, M.Schyns, S.V.Dyck, S.Michiels, H.A.Abderrahim

    9.3 217

    H.Nagata, T.Yamaura, M.Naka, K.Kawamata, H.Izumo, N.Hori, Y.Nagao, T.Kusunoki, M.Kaminaga, Y.Komori, M.Suzuki, M.mine, S.Yamazaki, S.Ishikawa, K.Miura, S.Nakashima, K.Yamaguchi, H.Kawamura

    10. 223

    10.1 225

    M.Sugiyama, T.Torimaru, K.Chatani

    10.2 231

    K.Usami, A.Onozawa, Y.Kimura, N.Sakuraba, H.Shiina, A.Harada, M.Nakata

    10.3 XCT 235

    A.Ishimi, K.Katsuyama, K.Maeda, T.Asaga

    11. 239

    11.1 CERCA () 241

    Dominique GESLIN

    11.2 U-Mo/Al 249

    J.M.Park, H.J.Ryu, J.H.Yang, Y.J.Jeong, Y.S.Lee

    12. 255

    12.1 JAEA 257

    K.Yamashita, H.Murakami, N.Nakagawa, N.Arai, K.Matsuura, Y.Ohzeki

    12.2 JMTR 265

    N.Takemoto, H.Izumo, N.Hori, E.Ishitsuka, M.Suzuki

    12.3 271

    N.Takemoto, T.Imaizumi, H.Izumo, N.Hori, M.Suzuki, T.Ishitsuka, K.Tamura

    12.4 277

    H.Kawamura, E.Ishitsuka, Mohd Fairus Abdul Farid, Julia Abdul Karim,

    H.Izumo, Mohamad Puad Haji Abu, Muhd Noor Muhd Yunus, Mohd Ashhar Hj Khalid

    13. 283

    293

  • JAEA-Conf 2011-003

    1. Introduction

  • This is a blank page.

  • JAEA-Conf 2011-003

    The 4th International Symposium on Material Testing Reactors was held from December 5 to 9, 2011 at the Oarai Park Hotel, Oarai-town, Japan. This symposium annually congregates worldwide specialist related to Material testing reactor (MTR), to exchange experiences, insights and ideas for fostering a community network. The first symposium was held at Oarai Research & Development center, Japan Atomic Energy Agency (JAEA), Japan, on July 16th - 17th, 2008, the second at Idaho National Laboratory (INL), Unites States, on September 28th October 1st, 2009, and the third at Nuclear Research Institute (NRI), Czech Republic, June 21st 23rd, 2010. The 4th symposium was initially planned to be held at Argentina, however Puyehue volcano eruption at Chili unfortunately forced the symposium to change place. Then, JAEA held this symposium on behalf of the INVAP, Argentina.

    For the 4th Symposium, papers were called for the following areas: - National and international policies for strategic planning on MTR, - MTR utilization, irradiation and PIE technology, - Recent Operational Experiences, - New and innovative MTR designs, - Facility upgrades refurbishment, life extension and decommissioning, - Nuclear regulation and licensing, - Human resources, training and qualification, - MTR fuels, design, manufacturing, and qualification.

    Total of 42 abstracts were applied for the presentation, and nine fields of sessions, including an invited session for circumstances surrounding research reactors, were planned. Finally, we have 39 presentations in the symposium as is shown in attached symposium program. Total 111 persons from 14 countries (Argentina, Belgium, Brazil, France, Germany, Indonesia, Malaysia, Philippines, Korea, South Africa, Switzerland, Ukraine, United States and Japan) attended the symposium. After 39 presentations, three topics, Necessity of cooperation for Mo-99 production by (n,gamma) reaction, Necessity of standardization of irradiation technology and Conceptual design of next generation materials testing reactor by collaboration were selected and discussed. Participants and presentations are shown in Figs.1and 2.

  • JAEA-Conf 2011-003

    Fig. 1 Participants of the 4th International Symposium on Material Testing

    Reactors.

    Fig. 2 Presentations of the 4th International Symposium on Material

    Testing Reactors.

  • JAEA-Conf 2011-003

    2. Circumstances Surrounding RRs in the World

  • This is a blank page.

  • JAEA-Conf 2011-003

    2.1 Research with Neutrons in Germany in View of the Phase Out of Nuclear Power

    Joachim Knebel1, Winfried Petry2

    1 Karlsruhe Institute of Technology (KIT) Chief Science Officer (CSO-4), Hermann von Helmholtz Platz 1

    D-76344 Eggenstein-Leopoldshafen, Germany Tel: +49 (721) 6082 5510

    E-mail : [email protected]

    2 Technische Universitt Mnchen Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II),

    D-85747 Garching, Germany Tel:+49 (89) 289 14704

    E-mail : [email protected]

    The central goals of German energy policy are guided by economic efficiency, security of supply and environmental compatibility. The German path towards an era of renewable energies requires intensified efforts and successes in innovation and new technologies in order to heavily accelerate the modification of the existing energy system. Priority is given to research and development in the fields of energy efficiency and renewable energies together with issues such as energy storages and energy grids.

    Thus, Germany has the potential and aim to develop into one of the most energy effective and environmentally friendly national economy world-wide.

    The deployment of nuclear energy for electricity production in Germany is limited to the year 2022 in order to allow the renewable energies to take this role, technologically and economically. In the frame of national provident research and to provide know-how in nuclear safety at the internationally highest level of science and technology, nuclear safety research is of high importance in Germany. This includes the operation of research and teaching reactors. National research centres and universities are equally contributing to both nuclear safety research and education and training.

    Traditionally Germanys research reactors focus on the delivery of intense neutron beams for basic research with neutrons. Both universities and national research centres within the Helmholtz Association are operating these neutron sources. Today Germany operates three neutron sources, the TRIGA Reactor operated by the University of Mainz, the swimming pool reactor BER2 operated by the Helmholtz Zentrum Berlin and the recently inaugurated multiple purpose Neutron Research Source Heinz Maier Leibnitz (FRM II). This is complemented by four teaching reactors at almost zero thermal power: at the TU Dresden, the University Stuttgart and the Universities of Applied Sciences in Furtwangen and Ulm.

    Beside this Germany is also stakeholder of the worlds most famous neutron centre, the Institute Laue Langevin at Grenoble, and is heavily engaged at the upcoming European Spallation Neutron Source (ESS) in Lund Sweden.

  • JAEA-Conf 2011-003

    This base of neutron beams of highest brilliance is used to give answers to the great challenges of modern society like Energy, Health, Information Technology, Mobility For example in Germany neutrons are used to cure tumors by irradiaton with fast neutrons, to produce homogenously doped Silicon for future high tension direct current transport or to reveal the physics of high temperature (Tc) supraconductivity.

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    JAEA-Conf 2011-003

  • Chi

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    JAEA-Conf 2011-003

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  • JAEA-Conf 2011-003

    2.2 Nuclear Research Policy in the Evolving Political Context of Switzerland

    J.-M. Cavedon, J. Dreier, P. Hardegger

    Paul Scherrer Institute Villigen PSI

    5232 Villigen Switzerland

    Tel : +41 56 310 27 42 E-Mail: [email protected]

    The five Swiss nuclear power plants cover 39% of its electricity needs. Together with the 55% hydro share, they bring an almost CO2-free electricity supply to the country since decades. In the aftermath of the Fukushima nuclear event, the Swiss Federal Council has rapidly frozen the ongoing process of general licenses for replacing or building new nuclear plants. It has proposed this summer to ban any new nuclear license, while letting the existing plants operate until the end of their life cycle, assumed to last 50 years in average. The Swiss nuclear plants were built between 1969 and 1984. A new energy strategy will be drafted by spring 2012, new measures and instruments will be submitted to the National Council and the Council of States in 2013, with final decision by public vote (referendum) in 2014. Ambitious targets for energy efficiency are being set: reduction of energy and electricity consumption of 13% by 2020, and of 28% (energy) and 35% (electricity) by 2035. No technology shall be forbidden and the Federal Council shall report regularly on the progress of energy technologies, especially on new nuclear technologies and their safety and waste reduction capabilities. The Paul Scherrer Institute acknowledges this political will. In agreement with the vast majority of the federal councilors and members of the parliament, it considers that nuclear energy research must be pursued. Nuclear power plants will be operated for decades and need safe operation with state-of-the-art safety measures and devices, as well as highly educated personnel. Nuclear research at PSI is already devoted to safety, waste management and new reactor concepts. This portfolio will be further pursued, with increased attention given to the educational potential of new reactors concepts, where increased safety and waste reduction are central topics. Highlights of todays research activities at PSI comprise materials degradation, passive safety integral tests, safety margins for fuel and cladding temperature, hydrogen risk, aerosol retention, dynamic probabilistic safety assessment and reactivity of fast neutron cores. All these topics contribute to the constant progression in reactor safety. The nuclear waste repository plans for Switzerland have converged on Opalinus clay as a host rock for deep underground repository. PSIs geochemical expertise is instrumental in assessing the safety of the repository concept and has contributed to the selection of six repository sites that are now formally approved for the second selection phase by all stakeholders.

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