Atomic Energy of Canada Limited

ADVANCED HWR POWER PLANTS

DL-11O

by

W. BENNETT LEWIS

Paper presented at the American Nuclear Society Power Division Conference Atlantic City, New Jersey 22-24 August, 1972

Chalk River Nuclear Laboratories

Chalk River, Ontario

November 1972

AECL-4304 PL-110

ATOMIC ENERGY OF CANADA LIMITED

ADVANCED HWR POWER PLANTS

by

W. Bennett Lewis

Paper presented at the American Nuclear Society Power Division Conference Atlantic City, New Jersey

22-24 August, 1972

Chalk River, Ontario November 1972

AECL-4304 DL-110

ADVANCED HWR POWER PLANTS1

by

W. Bennett Lewis

ABSTRACT

Heavy-water reactors that are near-breeders can be alternatives for fast breeder reactors with the capability of meeting all the world's needs for power for many centuries. The Canada Deuterium Uranium (CANDU) and Steam-Generating Heavy-Water (SGHW) reactors are the only types of heavy-water reactor established for high-power generating stations. Those CANDU reactors now operating and under construction in large unit sizes are fuelled with natural uranium and cooled and moderated with D20, meeting the requirements of utilities desiring a minimum of enrichment together with an attractive capital cost. Possible modifications to design are the use of boiling light water as coolant, organic coolant, and thorium fuel cycles. Heavy-water reactors have a worldwide distribution. They can be classified as follows: 1) zero energy lattice and reactor physics research reactors; 2) high flux materials test, neutron beam and isotope production reactors; 3) engineering test reactors with high temperature loops; 4) demonstration power reactors; 5) prototype power reactors; and 6) commercial power reactors. Operating experience with the large 540 MW(e) commercial units in Canada has been extremely satisfactory.

1 Paper presented at the American Nuclear Society Power Division Conference, Atlantic City, New Jersey, 22-24 August, 1972.

Chalk River, Ontario November 1972

AECL-4304 DL-110

Centrales a eau lourde avancees1

par

W. Bennett Lewis

Resume

Les reacteurs a eau lourde quasi-surgenerateurs peuvent concurrencer les reacteurs surgenerateurs rapides, car ils ont le potentiel voulu pour repondre aux besoins en energie du monde entier pour des siecles a venir. Les reacteurs CANDU (Canada Deuterium- Uranium) et SGHW (Steam-Generating Heavy-Water) sont les seuls types de reacteurs a eau lourde etablis pour les grandes centrales electronucleaires. Les reacteurs CANDU actuellemont en service ou en construction pour de grandes centrales sont corpus pour utiliser de I'uranium naturel comme combustible et de I'eau lourde comme moderateur et com me caloporteur. Ces reacteurs respondent aux exigences des fournisseurs d'electricite qui veulent un minimum d'enrichissemcit et de raisonnables depenses en immobilisation. Les modifications susceptibles d'etre apportees a la filiere CANDU sont: 1'emploi d'autres caloporteurs (eau legere bouillante ou liquide organique) et l'adoption du thorium dans les cycles de combustible. On trouve des reacteurs a eau lourde dans le monde entier. On peut les classer de la facpn suivante: 1) reacteurs de rechevches sur la physique des reacteurs ayant un reseau a energie nulle; 2) reacteurs pour la production d'isotopes, la formation de faisceaux neutroniques et 1'essai des materiaux en haut flux; 3) reacteurs pour les essais technologiques munis de boucles a haute temperature; 4) reacteurs de puissance en demonstration; 5) reacteurs de puissance prototypes et 6) reacteurs commerciaux de puissance. Une experience extremement satisfaisante a ete acquise au Canada dans le fonctionnement des grandes centrales commerciales a eau lourde ayant une puissance electrique de 540 megawatts.

1 Communication presentee au Congres de 1'American Nuclear Society, tenu a Atlantic City, New Jersey, du 22 au 24 aout 1972.

L'Energie Atomique du Canada, Limitee Chalk River, Ontario Novembre 1972

AECL-4304 ADVANCED HWR POWER PLANTS

by

W. Bennett Lewis

Advanced heavy-water reactor power plants are with light-water-reactors, would continue for a now established. Ths largest commercial station considerable time to prodrce plutonium for their use. already has an in-service capacity of 1,536 MW(e) net A further 512 MW(e) unit is due to be added next year and is on schedule. I have been pointing out for ten years or more that advanced heavy-water reactors could supply econotnic nuclear power to meet all the world's needs for very many centuries. The extent to which they will be developed and applied depends on the nature of the competition. There are, we know, large-scale plans to introduce fast breeder reactors, but over the next century if they are introduced, they seem likely to depend heavily on other types of power reactor for their plutonium fuel. This was illustrated by J.R. Dietrich in Fig. 1, which he presented at the Winter Meeting of the American Nuclear Society in 1966. His curves relate to the USA but tbe world situation Figure 1 is similar, with only the capacities increased by a factor of 2 or 3. To check in on his projected nuclear On the other hand, as I have said before, if the fast capacity, note that in 1980 his figure was just short breeder reactor is not an economic success, nothing of 100,000,000 kW, whereas now the USAEC very serious happens, provided that other advanced estimate is about 140,000,000 kW. Dietrich's postu- neutron economical nuclear power plants have been late was that in 1985 all the accumulated inventory introduced and carry on. There would, however, be of plutonium from the power reactors was committed no longer a special requirement for plutonium and to fast breeders. Focusing attention on the middle there seems a very strong probability that the con- curve for the 20-year doubter, we note that verter reactors would operate on the thorium- 40,000,000 kW was to come into operation in 1985. ranium-233 cycle which in the long term is most Large, but I suppose not impossible. Thereafter the economical for thermal neutron reactors. breeder curves show their growth if they derive their I am emphasising that the heavy-water power inventory solely from their own operations, then they plants are being developed and built not merely as would uinount to only a very small fraction of the an interim measure before fast breeder reactors are total nuclear power. For example, in the year 2005, established, but in their own right and, in the limit, to the curve shows 80,000,000 kW from the fast supply power and recycled fuel for all the energy breedfir, which is only 8% of the total projected needs that may arise in the world. nuclear capacity. The slope of that projected nuclear capacity is still greater than that of the 20-year In this context neutron-economical reactors doubter, so that the fraction provided by the 20-year command special attention. All the CANDU family of doubler would become even smaller. It is more reactors, whether cooled by heavy water, boiling light realistic to suppose that if the fast breeder reactor is water, or organic coolant, belong essentially to the an economic success, heavy-water-reactors, together neutron-economical or near-breeder class. They

-1- promise especially well in association with the (3) Engineering Test Reactors with High Temperature helium-cooled high temperature graphite moderated Loops reactors which benefit especially from uranium-233 (4) Demonstration Power Reactors fuel and a thorium cycle. It is encouraging to note (5) Prototype Power Reactors that many million kW capacity of such high tempera- ture reactors seem likely to be built in the next (6) Commercial Power Reactors Operating or Under twenty years. When associated with such reactors the Construction at June 1972 special merits of the heavy-water reactors are their The lists omit the Savannah River Reactors, DAPHNE efficient use of uranium-235 or even low enriched the Handmaiden Reaclor, Core II of the EBWR and uranium for initiating the production of uranium- at least one of the USSR experimental reactors. Some 233, for example in the cycle 1 have called the others may have been omitted unintentionally. In valubreeder.(l) each list the reactors appear roughly in the order of Heavy-water-moderated reactors have a long and their commissioning. To those who have followed worldwide history. The list of such reactors is too their fortunes their names may serve to recall long even to recite their names here. Many of them memories of international visits and collaboration. have been multipurpose and there is perhaps no Those who have become narrowly embedded in the better example than the Canadian NRX reactor that fates and fortunes of other types of nuclear reactors has recently passed its 25 year jubilee going strong may take away just an impression of their wide range, and still generating information for power reactors in geographical distribution and their continuing intro- mcny families. For example, a paper by R.C. Daniel duction. on Dimensional Changes in Zircaloy-4 Tubing from Of most interest here will be the last three lists of Admiral Rickover's Light Water Breeder Development the Demonstration, Prototype and Commercial Power Program appeared in May in the ANS Journal Nuclear Reactors. Ontario Hydro as the owner-operator and Technology reporting work in an NRX loop. Another Atomic Energy of Canada Limited as the nuclear loop carries organic liquid coolant in work towards designer are more than satisfied with the first year of heavy-water-moderated organic-cooled power reactors. NRX received a new calandria for its core in operation of the Pickering Nuclear Genorating Station 1953 after melting some metal fuel in a power near Toronto. The most encouraging feature shown excursion. Us fuel has changed from natural uranium on List 6 has been the successive reduction in time metal, through natural UCK with enriched boosters to from first critical to achieving "In-service" rating. For fully enriched fuel. Last year its calandria core vessel Unit 1 it was 154 days, for Unit 2 106 days, and for was changed again, ana operation was resumed in 130 Unit 3 only 38 days from 24 April to 1 June this days, a little under schedule. The first purpose of year. The availability during these commissioning NRX was as a prototype for producing plutonium in periods and after was high, as shown in Fig. 2. Even a high neutron flux. This helped to pioneer the way at the higher price now current the cost of the for the great Savannah River heavy-water-moderated heavy-water upgrading and loss amounted only to "production" reactors as well as for the 200 MW(t) 0.12 m$/net kWh. The fuelling cost cannot be NRU reactor that later has supported directly the fuel established so quickly but Ontario Hydro have channel development for the commercial 540 MW(e) indicated there is reason to expect it will be comfor- Pickering reactors. U is mainly to the needs of the tably less than 1 m$/net kWh. In the other CANDU Savannah River reactors that the world owes the reactors so far, we have used booster fuel rods cooled large-scale production of heavy waier that has by the moderator to override Xenon-135 poison for enabled the large number of heavy-watei-moderated 30 to 45 minutes after a shutdown. A departure has reactors shown in the following six lists to been made in the Pickering reactors that will reduce operate.'2H3) Despite the mu'tiple purposes of many the fuel burnup but not increase the total fuelling of these reactors, they are listed as cost. There are cobalt absorber rods normally in the core to make cobalt-60 for sale. These rods are withdrawn on a shutdown to provide the excess (1) Zero Energy Lattice and Reactor Physics reactivity needed for Xenon-override. Our calcula- Research Reactors tions on reactivity have been well sustained so it (2) High Flux Materials Test, Neutron Beam and seems safe to assess the fuelling cost as meeting Isotope Production Reactors expectations.

-2- PICKERING G.S. PERFORMANCE SUMMARY place). We have been able to reduce the radiation UNIT I fields that had built up, especially in the boiler room n at Douglas Point, by a factor of about six. The method is to impart a shock to the system by shutting the reactor down; this dislodges some of the deposited activity. At the same time extra by-pass circuits are valved in with filters and ion-exchange resin columns. The method is not equally successful in all circumstances so development is continuing on filters and means of changing the pH and oxidising potential of the primary coolant fairly abruptly. Fortunately the problem has been eliminntcd entirely in the organic liquid cooled reactor by the chemical control adopted to allow the use of zirco- Figure 2 nium alloys which proves quite simple. The success of these first commercial units implies C - experience from fuel in Douglas Point indi- that the necessary team work has been established eaioa we might expect fuel ruptures to affect about 1 between industrial manufacturers, engineering con- percent of the fuel bundles late in their life and these tractors and the quality control, commissioning and appear to be occurring. The economic penalty of 1% operating groups of the utility. This overall compe- on about 0.3 m$/kWh is negligible but the problem is tence is quite as important as the neutron economy not so simple. Although the faulty fuel can be for the expansion that lies ahead. removed on-power as soon as it is detected and located, there is a tendency to procrastinate until the In proceeding to the larger 750 MW(e) reactors Tor failure is aggravated by the waterlogging process and the Bruce Generating Station, advances in lite much higher levels of fission products build up in the computer control techniques already used in Pic- coolant, obscuring a possible new defect. As designers kering are incorporated, and further reductions in the we recommend removing a faulty fuel bundle at the number of valves, especially at the higher tempera earliest indication of failure. Also we recommend a tures, have been made. Larger pumps are being more expensive fuel less likely to fail, but naturally it developed. The station layout has also been consi- takes time to settle into the best compromise. We are derably changed. The main features, however, of tbu on our way; although there is some failed fuel that horizontal reactor design and short fuel bundle:- in has been allowed to remain in Pickering I it has not 10.3 cm dia. tubes are retained. yet restricted the operating performance. Sometimes The list (List 6) of commercial power reactors I woriy :!ial our better fuel now being manufactured ordered is expected to grow longer in the next few as the replacement fuel for Pickering under the name months with not only additional units for Ontario CANLUB fuel will be so good that a still better design Hydro but also for other provinces in Canada. will never be made. Overseas prospects have not moved so rapidly but could develop faster in the next two years. One After .is first year of operation, the turbine of delaying factor recently has been the temporarv Unit 1 ?*• Pickering has been down for examination shortage of heavy water that is expected to be and wan assessed as in good condition. Outages caused overcome by the end of 1974. by the steam and turbo-generator systems have been due to teething troubles and the remedies seemed We may look back to the prototype and demon- clear, so the plant is expected to settle down well. stration power reactors to see what is likely to join the established line. We have made some progress towards overtoiling a difficulty that is common to most water-cooied Three significant changes seem to Ik? ahead, reactors. It is the radiation exposure associated with namely the maintenance operations arisi*"^ from the transport (1) BLW coolant and deposition of radioactive corrosion products, (2) Organic coolant particularly Cobalt-60 in the coolant circuit (Cobalt- 60 is an enemy here although valuable in its proper (3) Thcrium fuel cycles

-3- As appeared in lists 4 and 5, four countries, the to designers of heavy-water-moderated boiling-light- U.K., Canada, Italy and Japan, have some commit- water-cooled reactors and it seems likely that one or ment to the boiling light-water coolant. The advan- more will be chosen to meet the requirements of tages are the elimination of a boiler or steam utilities desiring a minimum of enrichment, together generating heat exchanger, a slight gain in station with an attractive capital cost. There is no commit- efficiency and a major reduction in the leakage and ment yet to a commercial reactor of this type, but upgrading requirements associated with the hot there appear to be several possible openings. heavy-water coolant. The major disadvantages are a The organic coolant that appears so far only in series of design and operating complications arising reactors on List 3 has a different set of advantages from the variable density and hence neutron absorp- and disadvantages. The experience in the WR-1 tion in the coolant. There is also some loss of neutron reactor has been excellent and offers high promise. economy resulting in lower burnup in a natural The chief advantages are uranium fuelled reactor. Both effects are reduced by accepting some enrichment;, with or without the (1) High temperature operation to 400°C. has been addition of recycled plutonium in the fuel. The demonstrated over 3 years. Even higher tempera- recycle of plutonium is included in the Japanese fares, e.g. 425°C appear possible. design and is also under development in Canada. The (2) Practical chemical control has kept the coolant anticipated saving in capital from eliminating the circuit free from circulating or deposited radio- boiler is somewhat offset by the lower maximum activity, allowing immediate contact maintenance surface heat flux stably attained in a boiling system. when required on pumps or valves. In practice the maximum allowable is about 95 W/cm\ (3) Any leaks are readily visible and to some extent self-healing. This allows the possible use of To meet these design restrictions with natural normal flanged joints such as used in oil re- uranium fuel the Gentilly 250 MW(e) prototype has a fineries. relatively large but not costly fuel inventory and a limited power from a given size of channel. Also to (4) High surface heat transfer rates up to at least 320 2 overcome the instabilities from the variable density of W/cm have proved practicable. the coolant, extra sensors and controls are incor- (5) Neutror economy is similar to that with light- t porated to balance the flux level across the reactor. In water coolant, but coolant density changes are addition the protective shutdown system is sensitive more stable. to flux tilt and is fast acting and provided with (6) If desired it seems practicable to use uranium redundancy. The reactor reached full power opera- carbide fuel, with its advantages of higher density tion in June and the flux balance has been excellent. and thermal conductivity than oxide fuel. Further experience, however, seems desirable before designing a reactor of much higher power for natural (7) The pressure of the coolant need not be high. uranium fuel. The disadvantages are: A higher power density in the core is acceptable (1) it is necessary to provide against ignition and for fuelling with the addition of recycled plutonium flame propagation in the more volatile compo- or enriched uranium. Such provision is common to the U.K.. Italian and Japanese designs. A higher nents of the coolant that escape from any leak; power from the reactor seems attainable by this (2) although zirconium alloys have proved satis- means but no design for over 1200 MW(e) has yet factory to about 450°C, higher temperatures are been detailed. The U.K. SGHWR achieves good desired where engineering against hydride stability by using sufficient light water in the fuel accumulations at joints etc. has not been fully channels to contribute significantly to the neutron developed; moderation. The penalty is a loss of neutron (3) the coolant must be kept in motion to prevent it economy and the need for higher enrichment of the from depositing and coking; this has not proved fuel. The neutron economy becomes intermediate difficult; • between the CANDU reactors and the light-water- moderated reactors. (4) steam generator design for efficiency and limita- tion of effects of a tube break is still undeve- A good range of technical compromise is available loped;

-4- (5) it is necessary to provide continuing make-up of A peculiar property of thorium fuel in general was the coolant. emphasised at the IAEA 1967 Symposium on Heavy- 5 It may be noted that using uranium carbide fuel water Power Reactors^ ) Plain thorium-oxide fuel would permit the design of natural uranium reactors might be fabricated for a total cost of about with organic coolant to high power. $30/kgTh and after irradiation over two to four years v yielding 35 MWd/kgTh (worth, for example, $84 at The third anticipated developmer , namely the 0.1 m$/kWh), the credit from the residual value of application of thorium fuel cycles, is relev&nt to the the fuel would be about $200/kgTh. The compen- overall increasing dependence on nuclear power sating disadvantage is the need to supply neutrons throughout the world, that was discussed in the from some costly enriched fissile materi.'l or from a opening paragraphs. neutron source of some other type. The valubreeder We have reached the stage of considering very large concept mentioned earlier embodies the principle of power capacity. In this prospect very low fuelling, using thorium fuel for value and energy yield, operating and maintenance costs, less than 1 together with uranium at iow enrichment such as m$/kWh(e) seem attainable. An essential requirement 1.8% as the lowest cost source of spare neutrons. is high availability; that demands simplicity of the Other thorium fuel cycles of slightly higher cost offer plant and all auxiliaries, easy access to keep advantages of higher average power density and these maintenance time short, and a long unattended life for were discussed in the 1971 Geneva paper. Even on all components. Some of these characteristics are such a cycle requiring highly enriched uranium a offered by the organic coolant in heavy-water- 1,000 MW(e) reactor would require only about 25 Mg moderated reactors, others are offered by thorium of separative work units per year to be compared oxide fuel cycles. At the Fourth United Nations with 120 tj 150 Mg SW unite/year for a typical Geneva Conference on the Peaceful Uses of Atomic light-water reactor. Looking forward, however, to Energy in September, 1971, we described(4) a new these distant prospects it may be expected that other design of thorium-oxide fuel promising ratings as high means of providing the excess neutrons would also be as 50 to 80 kW(th)/kg Th, and yielding 35 MWd/kg developed, making the thorium cycle independent of Th over irradiations of two to four years with high natural or enriched uranium. neutron economy.

REFERENCES

1. W. Bennett Lewis "The Super-converter or Valu- 4. W. Bennett Lewis, M.F. Duret, D.S. Craig, J.I. breeder: A Near Breeder Uranium-Thorium Veeder & A.S. Bain "Large-Scale Nuclear Energy Nuclear Fuel Cycle" AECL-3081, May 1968. from the Thorium Cycle" AECL-3980. Paper A/CONF.49/P/157, 4th U.N. Int. Conf. Peaceful 2. Directory of Nuclear Reactors, Volumes II to IX, Uses of Atomic Energy, Proceedings Vol. 9, p.239, International Atomic Energy Agency, Vienna. 1971. 3. World Directory of Nuclear Power Reactors 1972. 5. W.B. Lewis "Outlook for Heavy Water Reactors" Nuclear Engineering International, Vol. 17, No. AECL-2947, Paper SM-99/37, Symposium on 191, April 1972. I.P.C. Business Press, 40 Bowling Heavy Water Power Reactors, Sept. 1967, Pro- Green Lane, London, EC1RONE. ceedings, pp. 545-55U, IAEA, Vienna 1968.

-5- HEAVY-WATER-MODERATED REACTORS LIST 1. ZERO ENERGY LATTICE AND REACTOR PHYSICS RESEARCH REACTORS

Commissioning Date Country or Site Reactor Month:Year

Chalk River ZEEP 9;45 France Zoe(EL-l) 12;48 Savannah River PDP 9;53 United Kingdom DIMPLE 7;54 (& 62) France Aquilon 8;56 Sweden R-0 5;59 Yugoslavia RB 4;58 USA Pawling PRR ;58 USA Aiken PSE ;58 Chalk River Zed-2 9;60 Japan AHCF 6;61 (& 8;63) India Zerlina ;61 Norway NORA 6;61 United Kingdom, Winfrith JUNO 4;64 Belgium Venus 4;64 Cadarache EOLE 12;65 Ispra ECO 12;65 S. Africa Pelinduna — Pelindaba -Zero 11;67

HEAVY-WATER-MODERATED REACTORS LIST 2. HIGH FLUX MATERIALS TEST, NEUTRON BEAM AND ISOTOPE PRODUCTION REACTORS

Commissioning Date Power Country or Site Reactor Month;Year MW thermal

Chicago CP-3 5;44 0.3 USSR Moscow TR 4;49 (7;57) 2.5 Norway Kjeller JEEP-1 8;51 (3;56) 0.45 France EL-2 10;52 2 Chicago CP-5 (ARR) 2;54 5 Harwell DIDO 11;56 10 Harwell PLUTO 1O;57 10 Australia HIFAR 1;58 10 Dounreay DMTR 5;58 10 USA MITR 7;58 5 Denmark DR-2 8;59 10 Yugoslavia RA 10;59 6.5 Ispra ISPRA-1 11;59 5 Karlsruhe FR-2 12;59 12 to 44 Switzerland DIORIT ;60 30 Japan JRR-2 10;60(10;62) 10 Germany Julich FRJ-2 ;62 15 Brookhaven HFBR ;64 40 USA GTRR 12;64 1 to 5 USA Ames ALRR •64 5 USA Gaithersburg NBSR ;65 10 to 25 Norway Kjeller JEEP-2 ,66 2 Grenoble von Laue-Langevin 57

-6- HEAVY-WATER-MODERATED REACTORS LIST 3. ENGINEERING TEST REACTORS WITH HIGH TEMPERATURE LOOPS

Commissioning Date Power Main Country or Site Reactor Month;Year MW thermal Coolant

Chalk River NRX 7;47 30-40 LW France EL-3 7;57 15 COj Chalk River NRU 11;57 200 HW Oak Ridge HRE-2 12;57 5 HW Norway Halden HBWR 6;59 20 BHW Hanford PRTR ;60 85 HW India CIR 12;60 40 LW Savannah River HWCTR 3;62 61 HW Japan JRR-3 9;62 (& 3;64) 10 HW Canada, Whiteshell WR-1 $3 20-40 OC Switzerland Lucens 5;68 30 COj ISPRA ESSOR In suspense 27 OC Taiwan TRR (72) 40 LW

HEAVY-WATER-MODERATED REACTORS LIST 4. DEMONSTRATION POWER REACTORS

Power Tube Regular UOj Fuel MWe or Power Op" percent Country Site and Reactor Net Vessel Month;Year Enrichment Coolant

Canada Rolphton NPD 20 T 9;62 Nat PHW (or BHW) Sweden Stockholm Agesta (R3-Adam) 10 V 3;64 Nat PHW USA Parr, Carolina, CVTR 17 T 12;64 1.5 + 2.0 PHW Germany Karlsruhe MZFR 57 V 12;66 Nat PHW France Monts d'Aree EL-4 70 T 10;67 1.4 CO, U.K. Winfrith SGHWR 94.5 T 1;68 2.3 BLW Italy Latina CIRENE 40 T (74) Nat+1.1 BLW

HEAVY-WATER-MODERATED REACTORS LIST 5. PROTOTYPE POWER REACTORS

Power Tube Regular UOj Fuel MWe or Power Op" percent Country Site and Reactors Net Vessel MonthjYear Enrichment Coolant

Canada Douglas Point G.S. 203 T 9;68 Nat PHW Czecho- slovakia BOHUNICE 112 - 71 — CO, Canada Centrale Nucl. de Gentilly 250 T 6;72 Nat BLW Germany Niederaichbach KKN 100 T (72) 1.15 CO, Japan Fugen ATR 200 T (76) 1.6 + 0.5 Pu BLW

-7- HEAVY-WATER-MODERATED REACTORS LIST 6. COMMERCIAL POWER REACTORS OPERATING OR UNDER CONSTRUCTION AT JUNE 1972

Power Dates Di 0 Inventory Stn. MW(e) Start-up In-Service Tonnes Effy. Turbine Country Site and Reactor Net Mo. Yr. Mo. Yr. Mod. Total Net MW RPM

Canada Pickering G.S. . UNIT 1 512 2 71 7 71 299 465 29.1 540 1800 (Ontario-Hydro) \ UNIT 2 512 9 71 12 71 299 465 29.1 540 1800 | UNIT 3 512 4 72 6 72 299 465 29.1 540 1800 ' UNIT 4 512 (73) 299 465 29.1 540 1800

Pakistan Karachi KANUPP 125 71 (72) 100 127 27.4 138.6 3000

India Rajasthan (BAPP-1 202 72 140 200 29.1 220 3000 1 RAPP-2 202 (741 140 200 29.1 220 3000

Argentina N. Buenos-Aires ATUCHA 319 (72) 300 300 29 340 3000

India Kalpakkam (MAPP-1 202 140 200 29.1 220 3000 Madras (MAPP-2 202 140 200 29.1 220 3000

Canada Bruce G.S. - UNIT 1 752 (75) 322 580 29.1 800 1800 (Ontario-Hydro) t UNIT 2 752 (76) 322 580 29.1 800 1800 1 UNIT 3 752 (77) 322 580 29.1 800 1800 " UNIT 4 752 (79) 322 580 29.1 800 1800 Total 5407

Note: All reactors are PHW-T-OP-Nat except ATUCHA which is PHWVSDNat. / PHW - Pressurized Heavy Water Coolant TuDe or Type ) ^'V Vessel | OP.SD - Fuelling on-Power or Shutdown 1 Nat - Natural UO, Fuel

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