BN-350 REACTOR SPENT FUEL HANDLING

Transcription

1 BN-350 REACTOR SPENT FUEL HANDLING Presented by Shaiakhmet Shiganakov Kazakhstan Atomic Energy Committee Technical Meeting, Oskarshamn, Sweden, April

2 The Map of Kazakhstan Nuclear Installations Disposition ASTANA Kurchatov Ust-Kamenogorsk Aktau BN-350 reactor ALMATY IAE NNC IRS & E INP Ulba metallurgical plant Uranium mines Research reactors Baikal-1 research reactors complex 2

3 State Structure for Atomic Energy Use Regulations PRESIDENT PARLIAMENT GOVERNMENT Ministry of Environmental Protection Ministry of Health Care Ministry of Energy and Mineral Resources Ministry of Emergency Situations Ministry of Internal Affairs Regional Branches Sanitary- Epidemiology Service Atomic Energy Committee Regional Branches Regional Branches Regional Branches 3

4 Main Factors Forming Nuclear and Radiation Situation in Kazakhstan National Atomic Company «Kazatomprom»: Uranium mine enterprises Plant of uranium concentrate production Fuel pellets fabrication plant (Ulba) Fast breeder reactor BN-350 (LLC «MAEK-Kazatomprom») National Nuclear Center: Research reactors Storage facilities for nuclear materials, radiation substances and radioactive waste Medicine, Science and Industries Enterprises : Organizations using radiation sources Transport organizations 4

5 IGR Pulse Graphite Reactor IGR research reactor is a pulse reactor on thermal neutrons with homogeneous uranium-graphite core of thermal capacity type. Technical Parameters Neutron flux maximum density n/cm 2 s Thermal neutron maximum fluence n/cm 2 Minimum half-width of impulse 0.12 s 5

6 IVG.1M Research Reactor IVG.1M research reactor is an upgraded version of IVG.1 reactor used for tests of fuel assemblies and cores of high temperature gas-cooled reactors Technical Parameters Thermal power 72 MW Core effective diameter 548 mm Core height 800 mm Uranium-235 content in the core 4.6 kg Thermal neutron flux density n/cm 2 s Water rate through the reactor up to 380 kg/s Maximum water temperature 950 С Baikal-1 Reactor Complex Reactor View from Reloading Machine Side Reactor Control Room 6

7 WWR-K Research Reactor A thermal neutron pool-type reactor. Coolant, moderator and reflector - desalted water. It was commissioned in 1967, operated at thermal power of 10MW till 1988 without deviations from standard modes. In period 1988 to 1998 the work was performed to enhance safety under high seismicity conditions. Since the core configuration was changed the thermal power was reduced to 6 MW without loss of neutron flux. Technical Parameters Thermal power 6 MW Fuel UAl 4 Loading 235 U 4.46 kg Enrichment 235 U 36% Core height 600 mm Experimental channel diameter 68 mm Thermal neutron flux density in the central channel n/cm 2 s 7

8 BN-350 Reactor Summary Operation period: Reactor type: fast breeder Thermal power (designed): 1000 MW(t) Electrical power (designed): 350 MW(e) Maximum thermal power achieved during operation: 750 MW(t) Layout: Three circuits Primary and secondary coolant: Na Number of loops in each side: Six Third circuit coolant: Water/steam 8

9 Main Decommissioning Documents Decree of the Government of the Republic of Kazakhstan #456, On Decommission of the Reactor BN-350 in the Aktau City of the Mangystau Region on April 22, 1999 Plan of Priority Measures (PPM) for BN-350 Reactor Decommissioning Main Provisions of the BN-350 Decommissioning Project 9

10 Decommissioning Strategy Phase 1 - Placement into SAFSTOR ( ) SF is unloaded from reactor core, packaged and placed in long-term storage LMC is removed, processed and radioactive products of the processing are placed in long-term storage LRW and SRW are processed and placed in long-term storage Systems and equipment, which are decommissioned at the moment of the reactor store, are disassembled Radiation monitoring of the reactor building and environment is provided Phase 2 - SAFSTOR ( for ~50 years) Phase 3 - Final Dismantling (after SAFSTOR) 10

11 Spent Fuel Handling Spent Fuel (SF) Packaging Manufacturing of cask (dual use type for transportation and storage) Construction of temporary storage site at MAEC, reloading stations at MAEC and in Kurchatov Construction of long-term storage facility in Kurchatov Transportation and placement for a long-term storage in BAIKAL site, Kurchatov (NNC RK) 11

12 SF Handling (continued) DOE and Kazakhstan designed and fabricated the canisters and packaging equipment Station for drying and welding canisters Packaging began in December Stainless steel canisters holding six or four assemblies are dried, welded, evacuated, and backfilled with argon The work was completed in Underwater Coincidence Counter

13 SF Handling (continued) Basic parameters Capacity 6 or 4 spent fuel assemblies. Dimensions: length 3989 mm, diameter mm; thickness of the side wall 4 mm; thickness of the protective lid 200 mm; Canister material stainless steel; Weight of the canister filled with the spent fuel assemblies 1500 kg. Internal media : The filled canister contains Ar gas, pressure 0.2 MPa. Total decay heat of single canister 500 W. The canisters with the spent fuel assemblies inside of the spent fuel pool of the BN-350 reactor. 13

14 SF Handling (continued) In February 2002 the United States proposed the approach using large metal/concrete casks for both transportation and storage (dual-use casks). Feasibility study was performed in September-December 2002 and has revealed the feasibility of this approach. Basing on the results of 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. 14

15 SF Handling (continued) Basic parameters Capacity : 7 canisters with the spent fuel assemblies. Transport Package consists of: Packaging Storage Set (PSS), including Metal Concrete Cask (MCC) and other parts (lids and etc.) Protective Damper Overpack (PDO). Weight and sizes: Packaging Storage Set : net weight 86 t height mm weight with SF 98 t diameter mm internal volume: 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 15

16 SF Handling (continued) MAEC s Interim Spent Fuel Storage Facility (Construction completion - February 2007) 16

17 SF Handling (continued) Spent fuel will be stored at Baikal-1 Baikal-1 site 17

18 SF Handling (continued) Special technical specification for SF dry cask storage facility has been developed (approved). Designing Task (requirements for Design of the temporary storage facility at the BN-350 site) has been developed (approved). Technical Tasks for Transport Package (approved) Technical Tasks for reloading site, long term storage at Baikal-1 site, and Scheme of transportation (TTS) (in process). Technical design of TP (in process) Technical Design of temporary storage facility at the BN-350 site (in process) Licensing Plans for KAEC is being developed for SF Transportation and Storage. 18

19 THANK FOR YOURS ATTENTION 19