Status of innovative small and medium sized reactor designs 2005 : reactors with conventional refuelling schemes

712 Pages·2006·22.846 MB·English

by  International Atomic Energy Agency

IAEA-TECDOC-1485
Status of innovative small and
medium sized reactor
designs 2005
Reactors with conventional refuelling schemes
March 2006
IAEA-TECDOC-1485
Status of innovative small and
medium sized reactor
designs 2005
Reactors with conventional refuelling schemes
March 2006
The originating Section of this publication in the IAEA was:
Nuclear Power Technology Development Section
International Atomic Energy Agency
Wagramer Strasse 5
P.O. Box 100
A-1400 Vienna, Austria

STATUS OF INNOVATIVE SMALL AND MEDIUM SIZED REACTOR DESIGNS 2005
IAEA, VIENNA, 2006
IAEA-TECDOC-1485
ISBN 92–0–101006–0
ISSN 1011–4289
© IAEA, 2006
Printed by the IAEA in Austria
March 2006
FOREWORD
There is a renewed interest in Member States in the development and application of small and
medium sized reactors (SMRs). In the near term, most new NPPs are likely to be evolutionary
designs building on proven systems while incorporating technological advances and often the
economics of scale, resulting from the reactor outputs of up to 1600 MW(e). For the longer
term, the focus is on innovative designs aiming to provide increased benefits in the areas of
safety and security, non-proliferation, waste management, resource utilization and economy,
as well as to offer a variety of energy products and flexibility in design, siting and fuel cycle
options. Many innovative designs are reactors within the small-to-medium size range, having
an equivalent electric power less than 700 MW(e) or even less than 300 MW(e). The
projected timelines of readiness for deployment are generally between 2010 and 2030.
The objective of this report is to provide Member States, including those just considering the
initiation of nuclear power programmes, and those already having practical experience in
nuclear power, with a balanced and objective information on important development trends
and objectives of innovative SMRs for a variety of uses, on the achieved state-of-the-art in
design and technology development for such reactors and on their design and regulatory
status.
The report is intended for many categories of stakeholders, including regulators, electricity
producers, designers, non-electrical producers and policy makers.
The main chapters of this report, addressed to all abovementioned groups of stakeholders,
provide a summary of major specifications, applications and user-related special features of
innovative SMRs, outline the achieved design and regulatory status and its progress since
previous IAEA publications, review targeted deployment dates, fuel cycle options, design
approaches used to meet design objectives in specific subject areas, enabling technologies and
current research and development (R&D) programmes in Member States, and non-technical
factors and arrangements that could facilitate successful development and deployment of
innovative reactors within the small-to-medium power range.
The annexes, intended mostly for designers and technical managers, provide detailed design
descriptions of innovative SMRs under development worldwide and are patterned along a
newly developed common format, which makes it possible to identify the design philosophy,
objectives and approaches, as well as technical features and non-technical factors and
arrangements with a potential to provide solutions in the specific areas of concern associated
with future nuclear energy systems.
Detailed design descriptions in this report were prepared firsthand by the designers and
reviewed, updated and approved for publication by the respective vendors, research and
design organizations and academic institutions in Member States.
The scope of this report is limited to reactors with conventional, proven in operation
refuelling schemes and does not include small reactors that could operate without reloading
and shuffling of fuel for a long period, from 10 years and more, with no fresh or spent fuel
being stored at the site during reactor operation. Because of a large number of inputs, such
reactors would require a separate dedicated publication.
The IAEA officer responsible for this publication was V. Kuznetsov of the Division of
Nuclear Power.
EDITORIAL NOTE
The papers in these proceedings are reproduced as submitted by the authors and have not undergone
rigorous editorial review by the IAEA.
The views expressed do not necessarily reflect those of the IAEA, the governments of the nominating
Member States or the nominating organizations.
The use of particular designations of countries or territories does not imply any judgement by the
publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and
institutions or of the delimitation of their boundaries.
The mention of names of specific companies or products (whether or not indicated as registered) does
not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement
or recommendation on the part of the IAEA.
The authors are responsible for having obtained the necessary permission for the IAEA to reproduce,
translate or use material from sources already protected by copyrights.
CONTENTS
1. INTRODUCTION ................................................................................................................ 1
1.1. Background............................................................................................................. 1
1.1.1. Developments in Member States ................................................................. 1
1.1.2. Previous IAEA publications ........................................................................ 5
1.2. Objectives .............................................................................................................. 6
1.3. Scope....................................................................................................................... 6
1.4. Structure.................................................................................................................. 8
2. DEFINITIONS, TERMS AND FORMATS FOR SMR DESIGN DESCRIPTION ........... 8
2.1. Definitions and terms ............................................................................................. 8
2.1.1. Small and medium sized reactors (SMRs).................................................... 8
2.1.2. Innovative design.......................................................................................... 9
2.1.3. Safety related terms....................................................................................... 9
2.1.4. Proliferation resistance related terms.......................................................... 12
2.1.5. Design and regulatory status....................................................................... 12
2.1.6. Enabling technologies................................................................................. 14
2.2. Formats for SMR design description ................................................................... 14
3. SUMMARY OF INNOVATIVE SMRs ............................................................................ 14
3.1. Innovative SMRs included in this report ............................................................. 14
3.1.1. Water cooled SMRs.................................................................................... 14
3.1.2. Gas cooled SMRs........................................................................................ 30
3.1.3. Liquid metal cooled SMRs......................................................................... 32
3.1.4. Non-conventional SMRs............................................................................. 34
3.2. Innovative SMRs not included in this report........................................................ 34
4. SUMMARY OF THE TECHNICAL FEATURES............................................................ 35
4.1. Introduction........................................................................................................... 35
4.2. Technical features and technological approaches used to improve
SMR economy...................................................................................................... 35
4.2.1. Water cooled SMRs.................................................................................... 36
4.2.2. Gas cooled SMRs........................................................................................ 36
4.2.3. Liquid metal cooled SMRs......................................................................... 37
4.2.4. Non-conventional SMRs............................................................................. 37
4.2.5 Summary of targeted economic characteristic............................................. 37
4.3. Provisions for effective resource utilization, waste management, and
minimum adverse environmental impacts.............................................................39
4.3.1. Water cooled SMRs.................................................................................... 39
4.3.2. Gas cooled SMRs........................................................................................ 40
4.3.3. Liquid metal cooled SMRs......................................................................... 41
4.3.4. Non-conventional SMRs............................................................................. 41
4.4. Summary of innovative safety features................................................................. 41
4.4.1. Water cooled SMRs.................................................................................... 42
4.4.2. Gas cooled SMRs........................................................................................ 43
4.4.3. Liquid metal cooled SMRs......................................................................... 44
4.4.4. Non-conventional SMRs............................................................................. 46
4.5. Technical features and technological approaches that support
proliferation resistance of innovative SMRs......................................................... 47
4.5.1. Water cooled SMRs.................................................................................... 47
4.5.2. Gas cooled SMRs........................................................................................ 48
4.5.3. Liquid metal cooled SMRs......................................................................... 48
4.5.4. Non-conventional SMRs............................................................................. 49
4.6. Technical features and technological approaches that facilitate
physical protection of innovative SMRs............................................................... 49
4.6.1. Water cooled SMRs.................................................................................... 49
4.6.2. Gas cooled SMRs........................................................................................ 50
4.6.3. Liquid metal cooled SMRs......................................................................... 50
4.6.4. Non-conventional SMRs............................................................................. 51
4.7. Conclusion to Section 4........................................................................................ 51
5. ENABLING TECHNOLOGIES THAT REQUIRE FURTHER R&D ............................. 51
5.1. Introduction............................................................................................................51
5.2. R&D for reactor core and fuel design....................................................................52
5.3. R&D for reactor internals and primary circuit.......................................................52
5.4. R&D for power circuit.......................................................................................... 52
5.5. R&D for safety concept, safety features and systems........................................... 53
5.6. R&D for technologies of fuel and materials fabrication,
fuel reprocessing and waste disposal.................................................................... 53
5.7. R&D for technologies of core refuelling, plant maintenance and
in-service inspection............................................................................................ 53
5.8. R&D for technologies and issues of NPP licensing, construction,
operation and decommissioning........................................................................... 53
5.9. R&D for calculation technologies and data sets................................................... 54
5.10. Available and planned tests facilities.................................................................... 54
5.11. Technologies for non-electric applications........................................................... 54
6. NON-TECHNICAL FACTORS AND ARRANGEMENTS THAT COULD
FACILITATE DEVELOPMENT AND DEPLOYMENT OF INNOVATIVE SMRs....... 56
6.1. Summary of the design descriptions..................................................................... 56
6.2. Addressing specific needs of certain markets at the design stage........................ 57
7. PROGRAMMES FOR INNOVATIVE SMR DEVELOPMENT IN
MEMBER STATES............................................................................................................ 58
7.1. Argentina............................................................................................................... 58
7.2. China..................................................................................................................... 59
7.3. France.................................................................................................................... 59
7.4. India...................................................................................................................... 59
7.5. Italy....................................................................................................................... 59
7.6. Japan..................................................................................................................... 60
7.7. Republic of Korea................................................................................................. 62
7.8. Netherlands........................................................................................................... 63
7.9. South Africa.......................................................................................................... 63
7.10. The Russian Federation......................................................................................... 64
7.11. The United States of America............................................................................... 66
APPENDIX I: Outline for SMR design description (full description).............................. 69
APPENDIX II: Outline for SMR design description (short description)............................ 73
APPENDIX II: Crosscut tables of ongoing and planned R&D; available or
planned test facilities.................................................................................. 75
REFERENCES .................................................................................................................... 89
DESIGN DESCRIPTIONS OF INNOVATIVE SMRs WITH
CONVENTIONAL REFUELLING SCHEME
DESIGN DESCRIPTIONS OF WATER COOLED SMRs
ANNEX I: System-integrated modular advanced reactor (SMART),
KAERI, Republic of Korea........................................................................ 93
ANNEX II: International reactor innovative and secure (IRIS),
International Consortium led by Westinghouse,
United States of America ........................................................................ 117
ANNEX III: Central Argentina De Elementos Modulares (CAREM),
CNEA, Argentina .................................................................................... 141
ANNEX IV: Multipurpose advanced reactor, inherently safe (MARS),
The University of Rome “La Sapienza”, Italy ........................................ 163
ANNEX V: Simple compact reactor (SCOR),
CEA, France............................................................................................. 195
ANNEX VI: Integrated modular water reactor (IMR)
Mitsubishi Heavy Industries, Japan......................................................... 225
ANNEX VII: Water cooled modular power reactor (VBER-300)
OKBM, Russian Federation .................................................................... 243
ANNEX VIII: Water cooled and moderated natural circulation boiling water reactor
(VK-300), RDIPE, Russian Federation................................................... 287
ANNEX IX: Compact containment boiling water reactor (CCR),
Toshiba Corporation, Japan..................................................................... 311
ANNEX X: Reduced moderation water reactor of 300 MW(e) (RMWR),
Hitachi Ltd, JAERI, JAPC, TITech, Japan.............................................. 335
ANNEX XI: Advanced heavy water reactor (AHWR), BARC, India ......................... 357
ANNEX XII: Reactor facility for district heating with atmospheric
pressure in the primary circuit (RUTA-70),
NIKIET, Russian Federation................................................................... 379
ANNEX XIII: Concept of a passive-safety reactor (KAMADO),
CRIEPI, Japan.......................................................................................... 405
DESIGN DESCRIPTIONS OF GAS COOLED SMRs
ANNEX XIV: Pebble bed modular reactor (PBMR),
PBMR, Ltd, South Africa........................................................................ 419
ANNEX XV: Gas turbine modular helium reactor (GT-MHR),
General Atomics, United States of America............................................ 451
ANNEX XVI: Gas turbine high temperature reactor 300
(GTHTR300), JAERI, Japan.................................................................... 487
ANNEX XVII: High temperature gas cooled reactor –
pebble bed module (HTR-PM), INET, China.......................................... 509
ANNEX XVIII: FAPIG high temperature gas cooled reactor (FAPIG-HTGR),
FUJI Electric, Japan................................................................................. 531
ANNEX XIX: Advanced atomic cogenerator for industrial applications
(ACACIA), NRG, Netherlands................................................................ 535
DESIGN DESCRIPTIONS OF LIQUID METAL COOLED SMRs
ANNEX XX: Korea advanced liquid metal reactor (KALIMER)
KAERI, Republic of Korea...................................................................... 553
ANNEX XXI: Modular plant with sodium cooled fast reactor (BMN-170),
OKBM, Russian Federation..................................................................... 579
ANNEX XXII: Modular double pool liquid metal cooled fast breeder
reactor (MDP), CRIEPI, Japan ............................................................... 601
ANNEX XXIII: Lead-bismuth cooled reactor with a high level of
natural circulation (RBEC-M),
RRC “Kurchatov Institute”, Russian Federation .................................... 615
ANNEX XXIV: Liquid metal cooled fast reactor for waste
transmutation and power production (PEACER),
Seoul National University, Republic of Korea........................................ 645
ANNEX XXV: Medium scale lead-bismuth cooled reactor, JNC, Japan......................... 669
DESIGN DESCRIPTIONS OF NON-CONVENTIONAL SMRs
ANNEX XXVI: The advanced high temperature reactor (AHTR),
Oak Ridge National Laboratory,
Sandia National Laboratories and
University of California, Berkeley, United States of America................ 675
CONTRIBUTORS TO DRAFTING AND REVIEW.......................................................... 701
1. INTRODUCTION
1.1. Background
1.1.1. Developments in Member States
In the early decades, civil nuclear power essentially borrowed from the experience of nuclear
submarine reactors, which came first and were essentially small sized reactors. Since 1970s,
the major focus for nuclear power was on the design and construction of nuclear plants of
increasing size, with average size levelling out at about 1000 MW(e) with a tendency for
further increase. This was and is generally appropriate for many industrialized countries,
which could add generation capability to their electrical grids in larger increments and benefit
from the construction costs reduced due to scale factor. However, it might be not appropriate
for many developing countries that have small electricity grids, limited capacity for
investment and less developed infrastructure.
At the time when this report was prepared (in 2005), 146 small and medium sized reactors1
(SMRs) were operated worldwide, accounting for 61 GW(e) of electricity generation, and 12
more were under construction2. These were mostly earlier generation reactors still in
operation and a few prototype or tests reactors, intended to support development and
deployment of new larger-capacity commercial plants. Their share in worldwide nuclear
electricity production was around 16.5%.
All analyses and forecasts of global energy needs project large increases in the century ahead.
For example, a projection from the International Panel on Climate Change [2] indicates that
primary energy demand in the world may double by 2050, see Fig. 1.
Many analyses reach the conclusion that nuclear energy has a strong role to play, particularly
if the goal is truly sustainable development3, not just temporary economic growth. For
example, the IPCC projection [2] indicates a 2.5 times median growth of nuclear power by
2030, see Fig. 2. The IAEA’s Nuclear Technology Review (2005 update) [5] projects a 34%
to 86% increase of nuclear generation by the year 2030.
The trends in the world at large contributing to increased expectations of the future role of
nuclear power, as identified in the Medium Term Strategy of the IAEA [6], are the following:
• The use of nuclear technologies in developing countries is growing as local
infrastructures improve and technology transfer increases;
• As the demand for electricity continues to increase and the drive for sustainable
development gains momentum, the need to exploit energy sources with limited
environmental impacts (in particular to meet commitments made in connection with
the Kyoto Protocol) could revitalize the nuclear power option.

1 According to the classification adopted by the IAEA, small reactors are reactors with the equivalent electric
power less than 300 MW, medium sized reactors are reactors with the equivalent electric power between 300 and
700 MW.
2 These data as of June 2005 are derived from the IAEA’s Power Reactor Information System [1].
3 According to the definition adopted by the Generation-IV International Forum [4], “sustainability is the ability
to meet the needs of the present generation while enhancing the ability of future generations to meet society’s
needs indefinitely into the future”. According to the definition adopted by the IAEA’s International Project on
Innovative Nuclear Reactors and Fuel Cycles (INPRO) [3], sustainable development is the “development that
meets the needs of the present without compromising the ability of future generations to meet their own needs”.
1