CURRENT STATUS ON FAST REACTOR PROGRAM IN KAZAKHSTAN

Transcription

1 CURRENT STATUS ON FAST REACTOR PROGRAM IN KAZAKHSTAN Presented at the 47 th Annual Meeting of the Technical Working Group on Fast Reactors IAEA, Vienna, May, 2014 by S. Andropenkov, National Atomic Company Kazatomprom

2 BN-350 DECOMMISSIONING BN-350 reactor was finally shutdown in April, 1999 according to Kazakhstan Government Decree Currently, according to the Plan of Priority Measures BN-350 is put in safestore condition 2

3 BN-350 decommissioning Plan of Priority Measures 3 Plan of Priority Measures for the BN-350 decommissioning (PPM) the main document that currently provides the framework for the reactor decommissioning. The reason for the PPM creation absence of the BN- 350 Decommissioning Project at the moment when the decision was made for reactor shutdown (April 1999). The main activities (PPM sections) reflect the specific features of the BN-350 reactor (handling with liquid metal coolant, spent nuclear fuel, accumulated in the spent fuel pool) and conditions of the reactor decommissioning (specifically, non-availability of the Decommissioning Project).

4 Main decommissioning activities PPM sections: 1. Measures on BN-350 decommissioning Project development. 2. Measures on safety provision of BN-350 during transitional period. 3. Measures on sodium drainage and utilization. 4. Measures on spent fuel arrangement for long term storage. 5. Measures on radwastes handling. 4

5 Major actions of the Plan of Priority Measures 5 Full fuel unloading of the reactor (completed) Packaging of spent fuel (SF) into sealed cans which provide additional safety barrier (completed) Primary Sodium cleaning of Cs, Sodium drainage into storage tanks (completed) Partial drainage of secondary sodium into storage tanks (completed) Processing of radwastes (in process) Buildings and structures preparation for Safestore conditions (in process) Main Provisions of the BN-350 NPP D&D Project were developed and approved.

6 Phases : (in accordance with Main Provisions of the BN-350 NPP D&D Project 1. Spent fuel arrangement for long term storage 2. Sodium coolant handling. 3. Construction of LRW processing facility. 4. Construction of SRW processing facility. 5. Preparation of reactor plant buildings and structures for long term storage 6. Completion of the BN-350 NPP D&D Project development 6

7 Spent fuel arrangement for long term storage ( 1 phase of construction) 7

8 History In February 2002 the United States proposed the approach using large metal/concrete casks (MCCs) for both transportation and storage (dual-purpose or dual-use cask) (DUC). To make the grounded decision on the approach offered by the USA the Kazakhstan Government requested that Preliminary Feasibility Study should be conducted for the version of dualuse cask in the Design proposed. This study was performed in September-December 2002 and has revealed the feasibility of this approach. 8 Basing on the results of Preliminary Feasibility Study, Kazakhstan Government decided to continue the activity for BN-350 spent fuel placement for long-term storage using dual use reinforced concrete cask.

9 Background Agreement for materials protection control and accounting of nuclear materials (MPC&A) between the US and Kazakhstan ministries of Defense has been prolonged in November In order to implement the work on the BN-350 spent fuel arrangement for long-term storage using dual use casks contract has been signed between NNSA (US DOE) and KATEP (Kazakhstan) in December

10 List of the main activities on SNF handling 10 Designing the TP and the non-standard equipment (completed) Designing the sites for temporary storage, reloading and the storage facility (completed) Manufacturing experimental TP, testing and licensing of the TP Construction of loading, reloading and storage sites; manufacturing, delivery and installation of necessary equipment (completed). Manufacturing of TPs, manufacturing of the equipment for TP transportation (completed) Transportation of BN-350 spent fuel and its arrangement for long-term storage (completed).

11 Scheme of SNF handling Contracts on manufacturing 60 transport packages were signed and manufacturing of TPs has been performed 11 spent fuel cooling pond Long Term Storage Facility at Baikal-1 site

12 Manufacturing TPs was completed on November

13 Basic parameters Capacity : 8 canisters with the spent fuel assemblies. Transport Package consists of: - Packaging Storage Set (PSS), including Metal Concrete Cask (MCC) - Protective Damper Overpack (PDO). 13 Weight and sizes: - Packaging Storage Set : net weight 86 t height mm weight with SF 98 t internal volume: diameter mm height 4120 mm diameter 1500 mm - Protective Damper Overpack : weight t length mm external diameter mm - Transport Package: net weight т length mm weight with SF t diameter mm

14 MAEK s Interim Spent Fuel Storage Facility before transportation 14

15 Long Term Storage Facility at Baikal-1 site after transportation 15

16 Sodium coolant handling ( 2-nd phase of construction) 16

17 Sodium handling Sodium cleaning from cesium Reactor drilling and sodium draining Sodium residuals removal Sodium processing into caustic Caustic processing into geocement stone 17 This work is supported by the US Department of State (DOS) through Nonproliferation and Disarmament Fund (NDF) and International Science and Technology Center (ISTC). Technical collaborator is ANL.

18 Sodium handling (continued) 18 The first stage consists of sodium cleaning from Cesium-137. The second stage includes the reactor internals drilling and draining of cleaned sodium into tanks of storage. The third stage of the sodium treatment consists of processing of drained coolant into sodium hydroxide with the following transfer into solid form acceptable for disposal. During the fourth stage remains of sodium were removed from inner parts of the reactor unit. The location of sodium after the bulk draining depended on design particulars of the reactor and circuits. The fifth stage is to transfer caustic into cementation compound, suitable for long-term storage and final disposal according to Kazakhstan regulations

19 ГЦН-I R Обратный клапан Задвижка Ду500 i=0.005 i=0.005 i=0.005 i=0.005 Задвижка Ду600 РЕАКТОР ПТО i=0.005 i= Axonometric drawing of the reactor vessel and a loop of primary circuit The method selected was bicarbonization with the following flushing with distilled water. Experiments were fulfilled in Kazakhstan National Nuclear Center to test regimes of sodium residuals removal.

20 BN-350 vessel internals 20

21 Drilling facility 21

22 Sodium handling What has been done 22 Development of drilling facility for drilling vessel internals. Development of special drainage channel. Manufacturing of drilling facility using experience gained on a mockup model. Restoring origin GHS of the reactor vessel as auxiliary heating source in case of emergency. As a result, cleaning the primary coolant from cesium has reduced activity in The drilling was performed at a depth of 13.4 m in sodium with temperature º C and drain the coolant from the reactor vessel and BN-350 loops was carried out, including measures for the storage of radioactive sodium before the processing. Sodium residues removed by using bicarbonization method from the reactor vessel, the loops of the 1st and 2nd circuits (removed about 400 kg of sodium).

23 SPF construction, start-up operations (completed) Geocementation facility design has been developed and construction is in progress Система отходящих газов (Off gas system) 2 - Емкость хранения (Storage tank) 3 - Бак суточный расходный (Day Tank) 4 - Емкость разбавления ( Dilution Tank) 5 - Реактор химический (Сhemical Reactor) 6 - Т/обменник (Heat exchanger)

24 LRW Processing facility (LRWPF) construction (3-d phase of construction) Current status 24 By the results of feasibility study a method of selective sorption has been selected. This approach has been confirmed by operation of pilot facility LRWPF Technical Design has been developed Expert review of LRWPF Technical Design has been conducted Engineering and geological survey for the construction site has been completed including for the storage facility site of RW solidified in containers LRWPF construction is in progress

25 Characterization of the BN-350 LRW LRW type: - stillage residue from the evaporation facilities; - sludge and sediments from the storage tanks bottoms Storage method: - gathering in concrete tanks, lined with stainless steel; LRW concentration: g/l. 25 Amount and activity of LRW to be processed: 3300 m 3 of distillate with total activity 3, MBq; 349 m 3 of sludge and sediments with total activity 7, MBq (including the sludge, produced during the processing). Nuclide composition: SWT facility for initial LRW processing at the BN-350 site Cesium-134,137, Strontium-90, Cobalt-60, Manganese-54, isotopes of uranium and plutonium.

26 Cementation facility Purpose: solidification of sediments and sludge by inclusion into concrete matrix (Portland cement of M-400/M500 grade, bentonite). Facility capacity: - On containers: 1 NZK per shift - On processed LRW: 1 t/h Sludge characteristics: - Cs-137 specific activity: up to 1, Bq/kg; - Co-60 specific activity: up to 1, Bq/kg; - salt concentration: up to 600 g/l 26 Cementation facility

27 NZK P containers Purpose: - storage of SRW of the 1-st and 2-nd category (on activity). Manufacturer: - JSC «345 mechanical plant», Balashikha city, Russia. Licence: - СУ , issued by Russian Gosatomnadzor. NZK P main technical parameters NZK P container Capacity: 1,5 м 3 Wall thickness: 150 mm Height: 1,38 м Concrete type: В50 (М700) 27 Width: 1,65 м Netto : 4,3 t Length: 1,65 м Brutto: Up to 7,3 t

28 SRW processing facility (SRWPF) (4-th phase of construction) During the BN-350 operation time (~25 years) 6800 tons of low and intermediate level waste have been gathered, 85% of the total amount is low level SRW, located in the trenches of SRW temporary storage at MAEC site. Existing temporary SRW storage does not meet up-to-date Kazakhstan nuclear safety requirements and should be decommissioned. SRW processing facility design has been developed 28

29 SRW retrieval from trenches To retrieve SRW from the trenches it is planned to use: 158V containment protective hangar structure, which in installed over the trench Brokk-330 manipulator with changeable heads; Transportation containers; Motor transport. 29

30 Preparation of reactor plant buildings and structures for long term storage (5-th phase of construction) By the results of Comprehensive Engineering and Radiation Survey (CERS), the scope of work has been determined, contracts signed and repairing of building has been started. For equipment Surveillance and Maintenance according to technological requirements. 30

31 Spent Fuel Bath Processing Facility The work was completed on designing the system for removal of content of tank #1 of the spent fuel bath (mixture of sodium-potassium, oil and their compounds). The work on removing the content of tank #1 of the spent fuel bath is in progress and content processing is in progress too. 31

32 Spent Fuel Bath Tanks Processing Facility 32 Facility for processing of Na-K from spent fuel bath tanks.

33 BN-350 Special System Handling (pending problems) Placement of 14 cold traps of primary, secondary circuits and Na-K cooling system into radiation and fire safe state for long-term storage and subsequent utilization; Handling of spent filters of special ventilation system (characterization, decontamination, storage); Upgrade of automated control system of LRW evaporating facility (Design, automation of LRW evaporating facility operation); 33