IAEA-CN-114/B-1 The Results of Russian Nuclear Civil Ships RP Operation and the Experience of their Specified Lifetime Extension V.I. Kostin1, Yu.K. Panov1, V.I. Polunichev1, O.A. Yakovlev1, M.M. Kashka2, N.V. Mantula2 1 OKB Mechanical Engineering (OKBM), Nizhny Novgorod, Russia 2 JSC "МSCO" Murmansk, Russia Abstract. The report presents the state of Russian nuclear fleet, gives short results of the nuclear ship reactor plants operation and the main causes influencing the damageability and residual life time of the most loaded units and elements of the systems and equipment. A list of modes decreasing the damaging thermocyclic effects upon RP elements is presented. Reactor plants state after the development of primarily determined reliability indices is analyzed, the practice of systems and equipment service life extension without factory repair is described. The results of the complex “Program of the Nuclear Ships NSSP Life Time Extension to 150000 hours and Service Life Extension to 30 years” (further called “Program …”) are presented; in accordance with this program OKBM and MMP together with the other organizations realize the measures provided in the “Program…”, first of all at the nuclear ice breakers “Arctika” and “Taimir”. Introduction Of the built nine nuclear ships seven are operated now, the nuclear ice-breaker “Lenin” is altered into a museum and the nuclear ice-breaker “Sibir” has a long-term closedown. The other ice-breakers are operated and with the existing now model of RP application they will reach the specified service life of 100 000 hours in 2004 –2009. Table 1 – Operating time of nuclear ships RPs Ship name "Arctika" "Sibir" "Rossia" "Sovetskiy Soyuz" "Jamal" "Taimir" "Vaigach" "Sevmorput" Average RP The year of operating putting into time a year operation (thousand of hours)* RP RP operating time operating RP service 100 000 hours time before life before 01.01.04, 01.01.04, The year of Service (years) (thousand life, operating of hours) (years) time end RP operating time 150 000 hours / 175 000 hours The year of operating time end Service life, (years) 1977 1985 6.22 6.88 95 96 19 18 2006*** 18 2004 / 2006 2012 / - 1989 6.58 78 14 2007 18 2015 / - 25 / - 1992 1989 1990 1988 6.2 6.77 6.53 6.53 65 95 87 86 11 14 13 15 2009 2004 2006 2006 16 15 15 18 2018 / 2012 / 2014 / 2014 / - 29 / 22 / 23 / 25 / - 1975 5.95 146 29 ** 1990 15 29 / 32 26 / - Note:* - The time of temporary ship closedown was not taken into account. ** - The operation of the ice-breaker “Sibir” was interrupted in 1992. *** - Ice-breaker “Rossia” will be removed from operation before 2005. 1 IAEA-CN-114/B-1 1 Operation results Altogether 15 reactors of OK-900 and KLT-40 type, the total operating time of which is 265 reactor-years are operated in Russian nuclear fleet. It should be noted that nuclear ice-breakers operation was more intensive, than it was first agreed in the performance specification for the RP because more than (85-90)% of time they operate in the ice under the conditions of high shock and vibration loads. Main RP equipment operated intensively and rapidly spent the life time, the periods of uninterrupted operation often lasted more than 10 months a year (table 2). Table 2 – Main operational data of nuclear ice-breakers and RPs before 01.01.04. Ice-breaker RP operating time, hours. Reactor power generation TW·hour. Average reactor power, %Nnom Р1 Р2 Р1 "Rossiya" Р2 "Sovetskiy Р1 Souyz" Р2 Р1 "Yamal" Р2 "Taimir" Р "Vaigach" Р "Sevmorput" Р 145508 146026 96016 95506 77541 77084 65439 65024 95059 87298 85515 9.521 8.641 6.519 6.473 4.971 5.082 3.893 4.478 7.492 7.435 4.574 0.38 0.35 0.40 0.40 0.37 0.39 0.35 0.40 0.46 0.50 0.40 "Arctika" Number of the performed core refuelings 7 6 3 3 3 3 2 2 5 4 3 The passed way (miles) Includin In total g in the ice Number of the conducted ships 954767 845067 3061 601242 540193 1555 406160 344456 698 384066 326713 828 531849 452578 314517 485089 394403 118476 1371 1064 - The designing organizations together with the operating organization (JSC “MMP’) worked at the perfection of individual RP elements and their operation conditions. Large work on the increase of the cores reliability have been performed. The first core sets mounted at the nuclear ice-breaker “Lenin” in 1970 at (0,9-1,1) ×106 MW/hr power output have practically reached the extreme state as for leak-tightness and the latest core sets successfully work out (1,9-2,6) ×106 MW/hr energy supply with practically leak-tight FE claddings. Some RP cores of nuclear ice-breakers exceeded specified energy supply without any features of loss of tightness owing to the reactor operation at the reduced average coolant temperature. Basing on operation experience a commercial core was developed, which is successfully operated at nuclear ships. During the whole period of nuclear ships operation there were no cases of their preschedule return from navigation to the port of destination because of RP failures. Though some equipment and systems had failures including small leaks from the primary circuit into the auxiliary circuits, there were no incidents with fission reaction control failure, uncontrolled radioactivity distribution and respectively people overirradiation. Qualified operation of the plant by the personnel using the hardware and parametric diagnostics available at the ship and constant author supervision helped to reveal the failures and malfunctions in proper time and to prevent their development and transition into the accident beforehand. The activities directed to RP safety increase were performed in the course of operation. For example, beginning from “Rossia” ice-breaker a new design of compensating group drive has been used. This design provides “self-movement” and has a step motor, developing larger forces than at the ice-breakers “Lenin”, “Arctica” and “Sibir”. Besides all CG drives have the possibility of CG working member insertion into the core with the help of manual drive. 2 IAEA-CN-114/B-1 To provide the guaranteed reactor transfer into subcritical state a system of liquid absorber injection into the reactor was introduced at those ice-breakers where it was absent. At the beginning of the ice-breakers operation the design of check valves fastening in the guide devices of the circulation primary circuit pump was improved and then they were substituted by the modernized ones. 60 steam generators were and are operated. The results of nuclear ships RP operation have demonstrated their reliable work. By the present time the specified lifetime and service life of all nuclear ships steam generators except the ice-breakers “Sovetskiy Sojuz” and “Yamal” have spent. At the operation beyond the bounds of the specified service life there was a considerable number of failures connected with the loss of intercircuit leak-tightness of tube system and with the necessity to disconnect some sections. JSC "ММP" made a decision to substitute tube systems at the ships where steam generators had spent their specified lifetime and had a considerable number of plugged sections. To reveal the reasons of steam generators failures in January 2002 the tube system of the icebreaker “Sibir” was cut-out and dismounted. In 2003 the tube system of the ice-breaker “Vaigach” was substituted. To reveal the place and the reasons of steam generator failures FSUE “Atomflot” began to fabricate specimens made of the tube systems of the ice-breakers “Vaigach” and “Sibir”, after it TSNII KM “Prometei” should perform laboratory investigations. The most dangerous are the failures connected with the primary circuit leaks which happened after the working out of the specified lifetime and were an object of special attention of the specialists. The performed metallographic investigations of the elements cut out from the equipment of the ice-breaker “Lenin” primary circuit and the results of the operation conditions analysis have shown that the main factors influencing the damageability and the residual lifetime are: - thermocyclic loads; - radiation effect; - pressure increase above the allowable value. The main reasons of the abovementioned loads are: - unstationary RP operation modes; - unregulated mass-exchange of cold and hot coolant with large temperature drop and small flowrates; - unregulated mixing of coolant flows; - cyclic mass-exchange of hot and cold coolants, stratification of the flows in the tubes with high temperature gradient; - unstable SG operation at low power levels. Due to thermocycling there were damages in the communications of pressure compensation system, in-reactor header and the others (see fig.1). These failures became an object of profound theoretical and experimental investigations of the equipment work at the operated and experimental plants. The investigation of thermocycling processes of the individual RP equipment systems allowed the development and introduction of operation modes decreasing the damageability of the most loaded RP units and elements at the operation beyond the bounds of the specified lifetime at OK-900A and KLT-40 plants: -to decrease the stresses in the elements and units of the reactor, SG and other equipment the rate of primary coolant heating and cooling is decreased from 100ºС/hour до 20ºС/hour; -to avoid unstable thermohydraulic operation of SG at low power levels at the primary coolant heating feed water supply to SG in different temperature ranges is provided by special algorithm and RP operation in power modes is provided at Nnom (15 - 100 %); 3 IAEA-CN-114/B-1 -to decrease the number of cold water throws to the heated SG piping the quantity of the circulation primary circuit pump transitions from high speed to low speed and back is limited; -to decrease the number of CG connections and quantity of thermocycles per pressure compensation system the rate of RP power change was lowered from 1%Nnom/s to 0,1%Nnom/s, number of power changes was decreased, the mode of interconnected control of RP and STP was excluded, the upkeep of the average primary coolant temperature is provided remotely in the expended limits by some definite algorithm; -to decrease the thermocycles of the filter cooler the disconnection of purification and cooling system is provided only at the cooled down system. Figure 2 –Schematic diagram of the ice-breaker “Taimir” primary circuit system. After the ice-breaker “Lenin” removal from operation there were a lot of works connected with cutting out of the specimens and investigation of the reactor vessel material, material of the weld between the tube system and steam generator vessel, filter cooler, circulating primary circuit plant, circulation cool down plant, one of biological shield units and the others. The dominating component of the reactor vessel life duration is its radiation life time. The activities on the irradiation and investigation of specimens materials cut out from the icebreaker “Lenin” RP reactor vessel and the additional specimens of materials of which the other vessels of the ice-breakers reactors have been manufactured, are continued. The correspondence of real radiational embrittlement of the reactor vessel materials to the prediction accessments was analysed. Evaluating calculations of radiation life time of the reactor vessels for 150000 hours and for 175000 hours were performed and primary coolant temperatures were determined at the performance of hydraulic tests taking into account the real content of admixtures in the reactor vessels materials. Circulating primary circuit pump which had 130000 hours operating time was dismounted at the ice-breaker “Arctica”, the specimens cut out from the most loaded units and details were investigated, the units and details deterioration was analysed, the conclusions on the subsequent circulating primary circuit pump serviceability were made. 4 IAEA-CN-114/B-1 Primary circuit valve DN50, which had 142500 hours operating time was dismounted at the ice-breaker “Arctika”, the specimens cut out from the most loaded units and details of the valve were inspected and their metal investigations were performed. The results confirmed the valve serviceability and the possibility to prolong its life time and analogous valves life time. The reactor head, circulating cool down pump, pressure compensation system pipelines elements of the ice-breaker “Arctika” have been revised. 2 The Practice of RP Equipment and Systems Operation Time Extension Primarily specified life time of the replaceable RP equipment was 50- 60 thousand hours at the service life of 20-25 years and the specified life of main equipment vessels was 100 thousand hours. The performed investigations and inspections of the main equipment of “Lenin” (performed after its removal from operation with the operating life of 110 thousand hours) and “Arctika” (performed at the operating life of 143 thousand hours) ice-breakers lead to the conclusion that there are considerable potential possibilities for the increase of the specified life time. The inspection has shown that after 131 hours of operation the circulating primary circuit pump remained completely serviceable. In particular there was no evident wear at the bearing supports; electric, mechanical and hydraulic characteristics had their design values. The same situation was with EP actuator and CG actuator drives, primary circuit valves, circulating reactor pump, DCO-2 devices and with other RP equipment. Metal investigations of main nozzles, of the reactor vessel metal in the area of the core, of the weld in the bottom area did not reveal considerable changes of materials properties or any other developing damages. It helped to develop the substantiated method of stage by stage extension of the vessels and replaceable parts of RP systems and equipment operation time to 100000 hours without factory repair. Operation time of the operated nuclear ships RP systems and equipment was prolonged stage by stage by (1-1.5) thousand hours, but not more than for one navigation (~5- 6 thousand hours) basing on positive results of examinations, inspections, calculational substantiation and performance of repairs in accordance with the developed programs. The results of nuclear ships operation during the prolonged period demonstrated high reliability of RP equipment and systems, large design margins. In this connection by the instructions of Russian government OKBM has developed “The Program of Nuclear Ships NSSP Equipment and Systems Lifetime Extension to 150000 Hours and Service Life Extension to 30 Years”. Besides in 2001 close corporation "TSNIIMF" developed a common program of extension “Nuclear Ice-breakers”. The purpose of the program was to determine the necessary efforts for inspection, substantiation and repair of the main equipment and structures of nuclear ships which extend their operation time. At present OKBM and public corporation “MMP” together with other organizations and enterprises realize the measures provided by the specified programs. 3 The Results of “The Program…” Realization In accordance with the requirements of the specified program the following was done: a) methods and means for nondestructive inspection of the technical state (accumulated operation damages and defects) of the equipment and pipelines metal and welds have been created; the accessories and inspection devices for the investigation of RP equipment elements and pipelines have been purchased and developed; b) complex inspection and examination of NPP systems and equipment important for safety using nondestructive inspection methods, safety systems with the exposure of reliability 5 IAEA-CN-114/B-1 indices, determination of the elements which spent their life time and should be replaced and the elements the life time of which may be extended for some definite time, is performed; c) acquisition and systematization of certification data on real mechanical properties of the main and welding materials and on the deviations which took place at the fabrication of equipment at the manufacturer plants was performed; d) acquisition and systematization of information and the analysis of operation experience of the systems, equipment and RP as a whole with the development of actual and predictable models of the systems, equipment and RP is performed; d) malfunctions and failures which took place at NPP operation are analysed and recommendations for their exclusion during the extended period are developed; e) metal investigations of the specimens and elements cut out of dismounted RP equipment, valves and pipelines (vessels, removable reactor block, pressure compensation system, circulating primary circuit pump and circulating cool down pump, filter cooler, biological shield pipelines of "Lenin" ice-breaker, “Vaigach” and “Sibir” ice-breakers SG tube systems, circulating primary circuit pump, reactor cover, valves, pipelines of “Arctika” ice-breaker pressure compensation system ); ж) calculational analysis of damageability and assessment of the residual life time of RP systems and equipment, including: 1) calculations of the defects development dynamics which were revealed after cutting out and investigation of the details and units of RP systems and equipment; 2) calculations for the substantiation of the concept “leak before break” adaptability to the primary circuit pipeline; 3) calculations for the residual life time substantiation. з) safety shortage is revealed, recommendations on its removal are made, compensating measures are proposed; и) in addition to standard operation modes technical and organizational measures and proposals directed to the mitigation of the influence upon RP pipelines equipment units and elements loading are developed; к) the programs of the life time control which allow the correcting of NPP equipment and systems important for safety operation models are developed. In case when real operation models considerably differ from the predicted ones the design substantiation of the subsequent operation of RP systems and equipment will be performed and if necessary additional recommendations and conditions for the decrease of the units loading, which limit the life time and service life, are given. Complex investigation of NPP and positive results of R&D performed by specially developed “Program of the Ice-breaker “Arctika” NSSP Life Time Extension to 175 000 Hours and Service Life Extension to 32 Years” allow the manufacturer plants the performance of some activities including ones for safety shortage removal and the substantiation of the possibility of RP and the ice-breaker as a whole operation time extension. In August 2003 mooring and sea trials of the ice-breaker “Arctika” RP were performed. Basing on the results of systems and equipment testing, including newly mounted ones it was determined that RP and its main characteristics correspond to the design values and “The Decision on the Ice-breaker “Arctika” RP Equipment and Systems Life Time Elongation to 175 000 Hours and Service Life Elongation to 32 Years” was made. Renovated ice-breaker “Arctica” is the first ship among Russian nuclear ice-breakers for which the activities on life time extension are under performance now. The activities on the ice-breaker “Taimir” RP service time extension have been begun. In 2003 the removable reactor block and the core which have spent its life time were substituted. The activities on central primary circuit pump, CPS CM drives and primary circuit valves certification were performed. By the middle of 2004 RP service life will be about 100 000 hours and the ice-breaker will return from Arctic for the performing of the other activities 6 IAEA-CN-114/B-1 necessary for RP service life extension to 150 000 hours. The termination of activities for the substantiation of the ice-breaker “Taimir” service life extension is planned to the 1-st quarter of 2005. The following ice-breakers coming to the necessity of RP service life extension are “Rossia” (2005) and “Vaigach” (2006). The extension of the operated and removed from operation nuclear ships life time has large economical efficiency. By the estimation of experts real and planned expenses for the performance of the repair (including vessel, pipeline, electrotechnical and other activities) in the period from 2000 to 2005 for the extension of seven nuclear ice-breakers service life will be about 1.5 billion roubles, that is about 20% of the cost of one universal two-draught nuclear ship construction (about 280 million US dollars). The total planned service life of the nuclear ships outside the limits of the initially specified life time will be about 55 icebreaker/years, it is equivalent to the complete service life of two newly constructed nuclear ships. It should be also taken into account that for the designing and construction of the head ice-breaker of new generation at the least 7-8 years are needed. 4 Conclusion The construction of the latest to date commercial ice-breaker “50 Let Pobedy” of “Rossiya” type will be completed not earlier than year 2005 (at the condition of enough financing). That is why we have to talk about the coming shortage of Russian ice-breakers, which can lead to the decrease of navigation period in Arctic. Positive results of the activities on “The Program…” allow the extension of the operated icebreakers service life to 2015. By this time it will be possible to build the ice-breakers of new generation which will solve the problems of freight service in Arctic and together with the available Russian ice-breakers confirm the priority of our country in the area of nuclear civil ship building. 7
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