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Status of Design Concepts of Nuclear Desalination Plants

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Status of Design Concepts of Nuclear Desalination Plants IAEA-TECDOC-1326 Status of design concepts of nuclear desalination plants November 2002 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 DESIGN CONCEPTS OF NUCLEAR DESALINATION PLANTS IAEA, VIENNA, 2002 IAEA-TECDOC-1326 ISBN 92–0–117602–3 ISSN 1011–4289 © IAEA, 2002 Printed by the IAEA in Austria November 2002 FOREWORD Interest in using nuclear energy for producing potable water has been growing worldwide in the past decade. This has been motivated by a variety of factors, including economic competitiveness of nuclear energy, the growing need for worldwide energy supply diversification, the need to conserve limited supplies of fossil fuels, protecting the environment from greenhouse gas emissions, and potentially advantageous spin-off effects of nuclear technology for industrial development. Various studies, and at least one demonstration project, have been considered by Member States with the aim of assessing the feasibility of using nuclear energy for desalination applications under specific conditions. In order to facilitate information exchange on the subject area, the IAEA has been active for a number of years in compiling related technical publications. In 1999, an interregional technical co-operation project on Integrated Nuclear Power and desalination System Design was launched to facilitate international collaboration for the joint development by technology holders and potential end users of an integrated nuclear desalination system. This publication presents material on the current status of nuclear desalination activities and preliminary design concepts of nuclear desalination plants, as made available to the IAEA by various Member States. It is aimed at planners, designers and potential end-users in those Member States interested in further assessment of nuclear desalination. Interested readers are also referred to two related and recent IAEA publications, which contain useful information in this area: Introduction of Nuclear Desalination: A Guidebook, Technical Report Series No. 400 (2000) and Safety Aspects of Nuclear Plants Coupled with Seawater Desalination Units, IAEA-TECDOC-1235 (2001). The IAEA officers responsible for the compilation of this report were M. Methnani and R. Faibish of the Division of Nuclear Power. EDITORIAL NOTE 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. CONTENTS CHAPTER 1. INTRODUCTION............................................................................................... 1 1.1. Background ............................................................................................................... 1 1.2. Objectives and scope ................................................................................................ 5 CHAPTER 2. OVERVIEW OF EXPERIENCE AND ONGOING ACTIVITIES .................... 7 2.1. Experience................................................................................................................. 7 2.1.1. Nuclear desalination system at Aktau, Kazakhstan ....................................... 7 2.1.2. Nuclear desalination plants in Japan.............................................................. 8 2.1.3. Nuclear desalination system in Pakistan........................................................ 8 2.2. Design approaches..................................................................................................... 9 2.2.1. Safety............................................................................................................. 9 2.2.2. Design life.................................................................................................... 10 2.2.3. Operational flexibility.................................................................................. 10 2.2.4. Reliability/availability.................................................................................. 11 2.2.5. Design limitations........................................................................................ 11 2.2.6. Economics.................................................................................................... 12 2.3. IAEA support programmes...................................................................................... 12 2.3.1. Co-ordinated research project (CRP)........................................................... 13 2.3.2. Development of an economic evaluation tool and its application ............... 13 2.3.3. Technical assistance through Technical Co-operation Programme (TCP)........................................................................................ 14 2.4. Relevant activities in Member States ...................................................................... 15 2.4.1. Argentina...................................................................................................... 15 2.4.2. Canada.......................................................................................................... 15 2.4.3. China............................................................................................................ 16 2.4.4. Egypt ............................................................................................................ 16 2.4.5. France and European Union......................................................................... 17 2.4.6. India ............................................................................................................. 17 2.4.7. Indonesia ...................................................................................................... 17 2.4.8. Republic of Korea........................................................................................ 18 2.4.9. Morocco....................................................................................................... 19 2.4.10. Pakistan........................................................................................................ 19 2.4.11. Russian Federation....................................................................................... 19 2.4.12. South Africa................................................................................................. 20 2.4.13. Tunisia..........................................................................................................22 CHAPTER 3. CO-GENERATION PLANT CONCEPTS UNDER EVALUATION............. 23 3.1. A small integrated PWR CAREM with RO and MED (Argentina)........................ 23 3.1.1. Background .................................................................................................. 23 3.1.2. Design description....................................................................................... 23 3.2. A small advanced integral PWR SMART with MED (Republic of Korea) ........... 27 3.2.1. Background .................................................................................................. 27 3.2.2. Design description....................................................................................... 33 3.2.3. Economic perspectives................................................................................. 43 3.3. PHWR and PWR with MSF (Pakistan) .................................................................. 43 3.3.1. Background .................................................................................................. 43 3.3.2. Design study for KANUPP .......................................................................... 45 3.3.3. Design study for large dual-purpose nuclear desalination plant .................. 47 3.4. PHWR with MSF/RO (India).................................................................................. 54 3.4.1. Background .................................................................................................. 54 3.4.2. Design description of the demonstration plant ............................................ 54 3.4.3. Project schedule and major milestones ........................................................ 58 3.5. PHWR CANDU with preheat RO (Canada) ........................................................... 61 3.5.1. Background .................................................................................................. 61 3.5.2. Design description....................................................................................... 61 3.5.3. Economic perspectives................................................................................. 65 3.6. Barge-mounted PWR KLT-40C with RO and MED (Russian Federation)............ 72 3.6.1. Background .................................................................................................. 72 3.6.2. KLT-40C, the energy source........................................................................ 72 3.6.3. Desalination processes for the nuclear desalination complex...................... 73 3.7. A small integrated PWR NIKA-70 with MED and RO (Russian Federation)........ 75 3.7.1. Background .................................................................................................
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