Rokkasho Reprocessing Plant (approx. 5.67MB)

Transcription

Rokkasho Reprocessing Plant (approx. 5.67MB)
ROKKASHO REPROCESSING PLANT
JAPAN NUCLEAR FUEL LIMITED
Rokkasho Reprocessing Plant is first commercial plant in Japan,adopting the technology
developed on the basis of more than 40years of operation results in both France and United
Kingdom, as well as operating experience gained by Atomic Energy Agency (JAEA).
C o n t en t s
Ⅰ
Ⅱ
Ⅲ
Ⅳ
Ⅴ
■1
Ⅰ Outline of the Plant
Schedule
Mar. 1989:Applied license for the reprocessing
business
Dec. 1992:Approval was granted on the reprocessing
business
Apr. 1993:Staeted construction
The first half of FY2018:Commissioning
18t
2007
● Rokkasho Reprocessing Plant
2■
Ⅱ Nuclear Fuel Cycle and
Reprocessing Plants in the World
3
5
3
Nuclear Fuel Cycle
Refining Plant
Uranium Mine
Conversion Plant
Uranium Hexafluoride
Recovered Uranium
Uranium Enrichment
Plant
Reprocessing Plant
Enriched
Uranium Hexafluoride
Vitrified Waste
Storage Center
Recovered Uranium
and Plutonium
Uranium
Dioxide
MOX Fuel
Fabrication Plant
Spent Fuel
Reconversion Plant
Uranium
Dioxide
High Level
Radioactive Waste
Recycle Fuel
Stock Center
MOX Fuel
Fuel Assembly
Spent Fuel
Underground
Storage Facility
Nuclear
Power Plant
Low Level
Radioactive Waste
■3
Fabrication Plant
Low-Level Radioactive Waste
Disposal Center
5
The Composition of Uranium Fuel for Light Water Reacter and MOX Fuel
Uranium Ore
U-235
approx. 0.7%
Uranium Fuel
(Before Irradiation)
U-235
3∼5%
Uranium Fuel
(After Irradiation)
MOX Fuel
U-235
approx. 1%
Plutonium
approx. 1%
Plutonium
4∼9%
Fission Products
approx. 3%
U-238
U-238
U-238
approx. 95%
U-238,etc.
4■
Ⅲ Reprocessing Plant
Process Outline
Receiving and Storage
Cask
Shearing and D
Cask
Spent Fuel
Cladding Tubes,
etc.
To be Placed in Containe
in the Storage Facility
■5
Dissolving
ers and Stored
Separation
Purification
Purification
of
Uranium
Separation
of FP
Denitcation
Storage of Products
Uranium Oxide Products
Separation of
Uranium and
Plutonium
To be Vitrified and
Stored
Purification
of
Plutonium
Specifications of Spent Fuel to be Reprocessed
Uranium-Plutonium Mixed
Oxide Products
Uranium
Plutonium
Fission Products(FP)
(High Level Radioactive Waste)
Metal Pieces, such as Cladding Tubes
6■
Receiving and Storage of
Spent Fuel
■7
Specification
8■
Shearing and Dissolution
From the Spent Fuel
Receiving and
Storage Process
Main Equipmemts
■9
Shearing-Blade Drive Cylinder
Main Fuel-Holder
Drive Cylinder
Shearing-Blade Holder
uxiliary Fuei-Holder
Drive Cylinder
Lid
Body
Fuel Feeder
End Piece Outlet
Hopper
(To End Piece Chute)
Sheared Fuel Pieces Outlet(To Sheared Fuel Pieces Chute)
Magazine
Spent Fuel Assembly
Fuel Inlet
Outline of Shearing Machine
10 ■
Separation
Nitric Acid
(HNO 3 )
Nitric Acid
(HNO 3 )
Nitric Acid
(HNO 3 )
Nitric Acid
(HNO 3 )
Nitric Acid
(HNO 3 )
Diluent
(normaldodecane)
Diluent
(normaldodecane)
Diluent(normaldodecane)
Diluent
(normaldodecane)
Main Equipments
Separation Facility extracts "uranium and plutonium" from the dissolved solution sent from the dissolution process.
And the second Facility separates "uranium" and "plutonium".
normaldodecane
normaldodecane
■ 11
Neutron Absorber(Boron-iaced Concrete)
Water Phase
(Nitric Acid Solution)
Inlet
12 ■
Purification
Diluent(normaldodecane)
Diluent(normaldodecane)
Diluent(normaldodecane)
From the Uranium-plutonium
Co-denitration Facility
Diluent
(normaldodecane)
■ 13
Main Equipments
As a result, impurities in the organic solvent containing plutonium will be rebuced.
normaldodecane
14 ■
Denitration and
Product Storage
Seal Vessel
主 な 仕 様
■ 15
Off Gas Outlet
Blowback Air Inlet
Candle Filter
* :Fluidized-bed is a state in which particles
behave as liquid, when small particles filled in
a container are blown with gas from the bottom
(UO3 particles in the case of Uranium Denitration
Facility).
For microwave heating, the same frequency is used
as microwave oven for home use.
Microwave Generator
Body
Microwave Leader
Seed Powder Inlet
Body
Electric Heater
Spray Nozzle
Mixed
Solution
UO3 Powder Outlet
Denitration
Dish
Molten Salt Outlet
Internal Heater Tubes
Molten Salt Inlet
Fluidizing Ari Inlet
Underflow Nozzle
Turn-Table
Outline of the Denitration Column
In the Denitration Column that is installed in the
Uranium Denitration Facility, air is supplied from the
lower part of the column to form the fluidized bed of
the UO3 powder. The uranyl nitrate solution is sprayed
into this fluidized bed from spray nozzles with air, and
electric heaters thermally decompose the solution at
approximately 300℃ .
Outline of the Denitrator
In the Denitrator that is installed in the Uraniumplutonium Co-denitration Facility, the mixed solution
of the plutonium nitrate solution and the uranyl nitrate
solution is surprised into the Denitration Dish, then
concentrated and denitrated by microwave.
16 ■
Recovery of Acid and
Solvent
Recovered Nitric Acid(To be Reused)
No.2 Acid Recovery System
Recovered Solvent (To be Reused)
normaldodecane
Main Equipments
■ 17
To the Separation Process,
Purification Process,etc.
Gaseous Waste
From the Shearing Machine,
Dissolver,lodine Desorder,etc.
From the Plutonium
Concentraton Feed Vessel, etc.
in the Purification Process
1st Oxidation
Columu,etc. in the
Purification Process
NOx
Scrubbing
Column
Heater,
Iodine Filter,etc.
To the Main Stack
Main Equipments
Shearing Off Gas and Dissolution Off Gas Treatment
Facility
HEPA Filter : 6 sets(composed of 2 stages)
Particle elimination efficiency : more than
99.9%(0.3μmDOP particle)/stage
Iodine Filter : 12 sets(composed of 2 stages)
Iodine elimination efficiency : more than 99.6%
Vessel Off Gas Treatment Facility HEPA Filter
Particle elimination efficiency : more than
99.9%(0.3μmDOP particle)/stage
Iodine Filter
Iodine elimination efficiency : more than 90%
HALW Vitrification Off Gas Treatment Facility
HEPA Filter
Column type : 4 sets(composed of 2 stages)
Box type : 2 sets
Particle elimination efficiency : more than
99.9%(0.3μmDOP particle)/stage
Iodine Filter : 2 sets
Iodine elimination efficiency : more than 90%
18 ■
Liquid Waste
(Low Active Liquid Waste (LALW))
Concentrated
LALW Storage Vessel
Main Equipments
■ 19
Liquid Waste
(High Active Liquid Waste (HALW))
Main Equipments
20 ■
Solid Waste
■ 21
Glass Material inlet
HALW inlet
Off Gas outlet
In the Virtification Melter, electric
Casing
current passes directly through the
glass by using electrode installed
in the furnace, and it melts by the
Molten Glass
Electrode
generating heat of Joule. The molten
glass in a Vitrification Melter is
Firebrick
Heating Coil
Air Nozzle
Flow down Nozzle
Flow down Glass
Off Gas outlet
Combination System
Canister
Solidified Glass
Vitrification Cell Transfer
Cart
poured into the canister by heating the
flow-down nozzle located at the lower
part of casing.
Palette
Weidht Monitor
Outline of Vitrification Melter
22 ■
Central Control Room
Analysis Facility
■ 23
Ⅳ Safety Measures
trays.
Schem of Multiple Protection against Leakage
24 ■
■ 25
Ⅴ Center For Research &
Development
26 ■
JAPAN NUCLEAR FUEL LIMITED
Reprocessing Business Division
4-108 Okitsuke, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori
TEL 0175­71­2000
Enrichment Business Division, Radioactive Waste Diposal Business Division
504-22 Noduki, Oaza Obuchi, Rokkasho-mura, Kamikita-gun, Aomori
TEL 0175­72­3311
Aomori General Office
Daiichi Seimei Building 1-2-15 Houcho, Aomori City, Aomori
TEL 017­773­7171
Tokyo Branch Office
Hibiya Kokusai Building, 2-2-3 Uchsaiwaicho, Chiyoda-ku, Tokyo
TEL 03­6371­5800
U R L h t t p : // w w w. j n fl . c o . j p /
2014. 10

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