Current Status of the KJRR Project and its Design Features Cheol PARK

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Current Status of the KJRR Project
and its Design Features
Nov., 17, 2014
Cheol PARK
0
Outline
Backgrounds
Project Overview
Design Overview
Concluding Remarks
1
Backgrounds

Counter measuring global shortage of Mo-99
 To secure the supply of key RI demands for medical & industrial uses

Growing demand of NTD
 To enlarge Si NTD services for power device market growth

Developing key RR technologies
 To be competitive in the world RR market
For these aims, the KJRR project was launched on 1st Apr. 2012 and the
planned schedule is 72 months from the conceptual design to
commissioning.
2
Chronology

Mar. ‘10 : Pre-evaluation by MOSF*

Jul. ‘10 : Site Selection by a committee of MSIP

Jun. ’11 : Feasibility Study completed by KDI

Dec. ’11 : Budget approval by the National Assembly

Apr. ‘12 : Official Launching & Conceptual Design

Apr. ‘14 : 3rd FY Start & Detail Design

Nov. ‘14 : PSAR Preparation for CP Application
* MOSF : Ministry of Strategy and Finance
MSIP : Ministry of Science, ICT and Future Planning
KDI
: Korea Development Institute
3
Project Overview
Project Name
Ki-Jang Research Reactor (KJRR) Project
Owner
KAERI (entrusted by Government)
Contractor (AE)
Daewoo & KEPCO E&C Consortium (‘13.4 contracted)
Contractor (PC)
To be later (in 2015)
Project Period
Apr. 1, 2012 to Mar. 31, 2018 (72 months)
Site
Ki-Jang District (near to Busan City)
▪ Design, Construction and Commissioning
Scope of Supply
- Reactor & Rx. building
- RIPF and Research Facility
- FM Production Facility with LEU target
- Rad-Waste Treatment Facility
▪ Administration Buildings
4
Key RR Technologies to be Developed

U-Mo Plate Type Fuel (1st Application to RR)
– Unique technology : Atomization Technique
– Long fuel cycle, Low fuel consumption

Fission Mo Production Technology
– Development of F-Mo production process with LEU target

Bottom Mounted CRDM
– Easy-access to the core

NTD Hydraulic Rotation System (NTDHRS)
– Convenient utilization (by hydraulically rotating the Si ingot)
to enlarge the RR utilization capability
5
Project Organization
Government
Local
Government
KAERI
Industry
KAERI
Conceptual Design
Basic Design
Fuel Design /Supply
Licensing
Eng. Company
(KEPCO E&C
& DW E&C)
Architect Eng.
Detailed Design
Construction
Construction
Commissioning
International
Collaboration
CRADA w/ INL
Cooperation w/IAEA
Vendors
RSA
MMIS
Component & Equip.
6
Project Budget
License & Site Investigation
Plant Construction
Fuel Design & Supply
RIPF & R&D Facility
LEU Target/FM Facility
Neutron Irradiation Facility
RTF
Site (130,000 m2)
Infra-Structure
 Entrance Road (two-lane)
 Elec.Supply(154kV, 20MVA-2)
 Water Supply(1,200t/day)
7
Project Schedule
Activities
Design of
Rx & Facility
Site Selection
&
Construction
2012
Conceptual
Design
2013
2014
Basic
Design
Detailed Design & SAR
2015
2018
2017
CDRM development & Fuel Qualification Test
Site
Investigation
Site
Preparedness
Excavation & Construction
Installation
Procurement, Fabrication and Installation
First
Critical
Licensing
Licensing
Commissioning
Procedures
Commiss.
& Operation
Output
2016
CAT/SPT/RPT
Normal
Operation
Operator Training
SIR
SER
 Construction
 RX Installation
 System Utilization
RER
PSAR & CP
CAT/SPT/IST & OL
RIT/Power Ascension
RI Production
Irradiation
service
※ Schedule depends on the budget, technology development etc.
8
Utilization

Radioisotope Production
 Mo-99 (To meet national demand increasing year by year)
 I-131, I-125, Ir-192
 Co-60, P-33, Re-186, Sm-153

Silicon & Wafer Doping
 5 NTD Holes for Irradiation of Si Ingot with 6” - 12“
 1 Hole for Fast Neutron Irradiation of Si Wafer with 8”
 R&D
 PTS & HTS
 Neutrino Test Station
9
KJRR Specification
Power
~15 MW
Type
Open Tank in Pool type
Max. thermal neutron flux
(n/cm2s)
> 3.0x1014 (Central Trap)
Operation day
~300/year
Life time
50 year
LEU Fuel
U-7Mo plate type (U loading : 6.5, 8.0 g/cc)
LEU Target
UAlx plate type (2.6 g/cc)
Reflector
Coolant and
flow direction in operation
Reactor building
Be , Gr
H2O,
Downward forced convection flow
Confinement
Decay heat cooling
Passive System
Robust Design, 0.3g SSE, Digital I&C, Cyber Security
10
Site
(1/3)
 Easy Access through International Airport, Port, Highway
11
Site
(2/3)

The site was selected through competitions among 9 local
governments that have expressed their wishes to host the KJRR.

The site is very close to Busan which is the second largest city in
Korea and has an international airport and a harbor which
provide good accessibility as well as easy transportation of
products.

The site is very close to several existing NPPs in operation. Thus,
it is expected that there is no difficulty in the site characteristics
including PA.
12
Site

(3/3)
Leveling of the site for construction started in July, 2014.
Location of Reactor Assembly
Meteorological Tower (from June, 2014)
13
General Arrangement
- accessibility, mobility, usability, safety, economy etc.
Reactor area
FM & RI production area
14
Pool Arrangement
15
Reactor Assembly
 Rx. Assembly
Expansion Joint
Assembly
 Rx. Structure assembly
Refueling Cover
Reactor Cover
Assembly
Upper Guide
Structure
- flow path, support structures
 Fuel assemblies
 Reflectors
 CRDM/SSDM below the Rx.
Core Box
Reflector
Assemblies
- 4 CRDM : motor-driven
Neutron Detector
Housing Assembly
Grid Plate
- 2 SSDM : hydraulically driven
Outlet Plenum
16 16
CRDM/SSDM Development
(1/2)
 CRDM/SSDM
 Being developed
 Qualification test schedule
 Completed all key components
development : Oct., 2014
 Test facility for performance and
endurance tests : Dec.2014
 Manufacturing of Q Class Prototype
CRDM/SSDM : May. 2015
 Performance and endurance tests of
CRDM/SSDM : June to Dec., 2015
 Test facility for seismic test : Mar.2016
 Seismic tests of CRDM/SSDM : Mar. to
June.2016
CAR/SSR Assembly
Follower Fuel Assembly (FFA)
ES adapter
CAR/SSR Extension Shaft Assembly (ESA)
Extension Shaft (ES)
CRDM/SSDM Seal Valve Assembly
CRDM/SSDM Connector Assembly
Armature Guide Tube Assembly
RC Electromagnet Assembly
CRDM Drive Assembly
17 17
CRDM/SSDM Development
Prototype Control Rod
(2/2)
Prototype Control Rod Guide Tube
Extension shaft adapter
CR Control System
Electromagnet &
Test Equipment
CRDM Assembly
18 18
Core Configuration
 Fuel
 Plate type (Typical MTR type fuel)


- 21 plates & 22 flow channels
Fuel meat : U-7Mo/Al-5Si
- 6.6 & 8.0 gU/cc
 Low fuel consumption
Fission Moly target : U-Alx
- 2.5 gU/cc
Fuel Assembly
Fission Mo
Target
SF
A
FF
A
 Core
 SFA(16)+FFA(6) in 7x9 lattice
- Same shape of SFA and FFA
 for flexibility in core management
 Fission Mo target (6)
 3 flux traps
 9 IRs with on-power loading
 PTS, HTS etc.
Core Box Configuration
19 19
U-Mo Fuel Qualification
Mini/Full length
Plates
Irradiation & PIE
Tests with 16 mini-plates
(will finish in June 2017)
A Prototype FA
Irradiation & PIE
Tests with full scale FA
(will start in Apr. 2015)
Plate wise
Irradiated data
Irradiation &
PIE at HANARO
& INL
Input to
RERTR
Test
Report
Manufacturing
Properties
Flow test
Finished in Mar. 2015
KJRR
SAR
Mechanical
Characteristics
20
Thermal Hydraulic Design

Normal Operating Conditions
Design Variable
Design Values
 Core power (fission, MW)
 No. of Standard Fuel Assembly
 No. of Follower Fuel Assembly
 No. of fuel plates/assembly
 No. of FM target plates/assembly
 Core inlet temperature (℃)
 Core outlet temperature (℃)
 Flow direction
 Core flow rate (kg/s)
- Fuel cooling channel
- Fission Mo target channel
- Gap flow
 Core pressure (kPa)
- Fuel inlet
- Pressure drop of fuel assembly
 Average core flow velocity (m/s)
- SFA/FFA
- Fission Mo target
 Average heat flux FA/FM (MW/m2)
15.0
16
6
21
8
35.0
41.3
Downward
535.0
432.8
47.6
54.6
180
86
Core
Inlet
FFA
Core
Outlet
6.0
7.5
0.415/0.748
21 21
Cooling Systems
 PCS
 SCS
 PWMS
 HWLS
 SRHRS
-
PWMS
SRMS
SRMS
SRMS
M
IX
M
SCS
Filter
Filter
HX
M
SRMS
Demi water supply
Service
Pool
Reactor
Pool
Standby
SCS
Filter
Standby
Decay heat removal
at PCS pumps unavailable
SRMS
SWS
IX
IX
SRMS
SRMS
S
S
Heater
Heater
HWLS
M
M
M
M
Siphon Break
Valves
Air
PCS
Flap
valve
Standby
Rx
Standby
DWST
SRHRS
LRMS
Spent Fuel
Storage
Pool
A
HX
POOL
WATER
STORAGE
TANK
DECAY TANK
Rotating hydraulically
Si ingot and cooling
reflector & target
IX
Filter
SRMS
 NTDHRS
-
M
A
SCS
A
HX
A
HX
Standby
Filter
Standby
NTDHRS
22 22
I&C Configuration



For Control, Protection, and Monitoring of Reactor Facility
RPS, RRS, PAMS, APS, ASTS, RASS, MCR, SCR, PICS etc…; commensurating with classifications
Digital technology is applied
23 23
Birds-eye View
24
Concluding Remarks
Through the KJRR project,

Contribution to the Nation
 Self sufficiency in terms of medical and industrial RI supply
 Enlarging and vitalizing the power device industry and RI industry

Contribution to the World
 First qualification & application of U-Mo fuel for RRs
 Increase of medical RI supply capacity in the world
 Sharing the knowledge and experience from the KJRR
25
Thank You !!!
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