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transcript
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Overview on the HTR-program
in Germany
Visit of the NRC-Delegation in Germany July 23-26, 2001
Dr. Josef Schoning
Westinghouse Reaktor GmbH Mannheim, Germany
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Overview on the HTR-program in Germany
HTR Development in Germany from the View Point of the Vendor
[7 When did we start this technology
0 Which status we have reached up to now
7 How far is this technology proven and usable for the PBMR project
71 BBC line - AVR, THTR, HTR 500, HTR 100, GHR, HHT, PNP
7 Siemens line - HTR Modul, PNP, Various studies
"EJ Concentration of the HTR development in the HTR GmbH because of marketing and cost reasons
"1 Common reactor line - HTR 500, HTR 100, GHR
"1 Design and R&D of the main projects Dokumentl
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Overview on the HTR-program in Germany
HTR Development in Germany
ters/ HRB HTR 1956 - development
BBR - design (LWR) - erection
- commissioning
CL{.500/o 50%
IA HTR 1975 - development
design erection commissioning
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o ] PNP ! 21 I , PN
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closed HRB 1993 (96) IA 1992 lllll. llmmi nil iiiiim m m u . lum i miimllil am . i i .m mll lmmll l ll l
today
*)BBC -. ABB-BNFL/WER
HTR GmbH still exists (new shareholders-WER/FAN P) - markt observation - providing of licensing and consulting contracts
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Overview on the HTR-program in Germany
Main Design Data
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AVR THTR HTR HTR HTR M GHR 500 100
Thermal Power MJ/s 46 750 1390 258 200 10/20
Net electrical power MW 15 296 550 100 80
Mean power density MW/m 3 2,6 6 6,56 4,2 3 0,8
Primary gas pressure bar 10,8 39 55 70 70 30
Hot gas temperature °C 850/95C 787 700 700 700 450
Cold gas temperature °C 275 262 260 250 250 250
Main steam pressure bar 72 177 180 190 190
Main steam temperature °c 500 530 530 530 530
Overview on the HTR-program in Germany
"AVR
General View on the Reactor
Feedwater line - -Main steam line
Steam generator
Inner tank
Upper shield
Upper reflector
Graphite columns for shutdown rods
Reactor casing
Reactor jacket
Lower reflector
Support
Materials:
Steel
Graphite E Coal brick
Rubble from Ma netit 1: andLimonit LJ
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Overview on the HTR-program in Germany
Built Plants Time Schedule
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AVR THTR
Start of Planning middle of '57 middle of '60
Order by utility group and start of construction 08/61 06/71
PCRV proof pressure test 09/82
First criticality 08/66 09/83
Functional tests (THTR)
Components and systems ly Total plant nuclear 0 - 40 % ly Power production on 40 - 100 % ly
First electricity to the grid 12/67 11/85
100 % power output 12/69 09/86
Handover to the customer 05/69 06/87
Decision for decommissioning End of '89 End of '89
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IOverview on the HTR-program in Germany
THTR 300 MWe Nuclear Power Plant
Hamm-Uentrop
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Overview on the HTR-program in Germany
THTR Longitudinal Section
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Overview on the HTR-program in Germany
THTR Dry Cooling Tower
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Overview on the HTR-program in Germany
THTR Fuel Handling System
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Overview on the HTR-program in Germany
THTR
Prestressed Concrete Reactor Vessel
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Overview on the HTR-program in Germany
HTR 500 Reactor Pressure Vessel with Internals
Prestressed concrete reactor vessel
-Main circulator
. Main steam line TFeedwater line
-Steam generator
-Thermal shield
Graphite reflector
-- Fuel element discharge pipe
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Overview on the HTR-program in Germany
HTR 500 Longitudinal Section
Reactor protection building
30,0 48,0 42,5 12,5 66,0
199,0
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Overview on the HTR-program in
HTR Modul Cross Section
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Germany
Overview on the HTR-program in Germany
HTR Modul Cross Section
Sol 100
Reactor pressure vessel Steam generator vessel Connecting pipe Primary coolant blower
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Primary shielding Full protection wall Liner cooLer Reactor building extension
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Overview on the HTR-program in Germany
GHR 10 Gas Cooled Heating Reactor
Prestressed concrete vessel
Graphite reflector
Core H;
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Overview on the HTR-program in Germany
GHR 10 Heat Flow Diagram
Inside reactor vessel Outside reactor vessel
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Overview on the HTR-program in Germany
GHR 10 Longitudinal Section
MAINTENANCE HALL
"DECAY HEAT REMOVAL SYSTEM
FACTOR PRESSURE VESSEL
22,20 1Sal 098
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Overview on the HTR-program in Germany
R & D Programs Subsidized by the Government
Project Partners Period Subsidy Totat % Cost*
Mio DM
THTR BBC/ HRB Nukem 64-88 95-100 -3200 FZJ (incL. erection)
HHT BBC / HRB Siemens / IA 69-82 60-90 ~ 200 Nukem FZL German industry Swiss industry
PNP BBC/ HRB Siemens / IA 76-92 75-90 150 Nukem FZL German industry
Others BBC/ HRB 82-88 50-90 ~ 100 (HTR500 Siemens / IA HTRIO0 FZL HTR Modu[ German industry GHRIO) Swiss industry
*in the figures the costs of FZJ and foreign partners are not incLuded
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Overview on the HTR-program in Germany
Scope and Depth of R & D
Core physics N and hydraulics
Model tests for . extrapolation laws
He-technology effects
Materials
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Tests of single elements
Prototype tests
Acceptance tests
Commissioning test
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Design of reactor
components
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Overview on the HTR-program in Germany
The R & D Programs
" materials - high temperature steel, ceramic material, prestressed concrete * physical and mechanical properties e.g. strength, creep,
fatigue "* fracture mechanics "* irradiation behaviour "* influence of corrosion "* tritium permeation
" elements and components "* fuel elements "* prestressed pressure vessel "* ceramic core internals "* heat exchanger - steam generator, He/He heat exchanger,
steam reformer "* shut down facilities - incore rods, reflector rods,
Small Absorber Spheres (SAS) "* fuel handling system "* gas ducts "* insulation "* Leak tight penetrations "* valves "* Leak tight joints e.g. screw joints, flanges
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Overview on the HTR-program in Germany
The R & D Programs
[ He-technology * friction * wear * bearing * welding * coating * sealing
7 pebble bed mechanics - e.g. flow characteristics, forces, abrasion
1 thermo hydraulics - e.g. leakages, bypasses,
gas mixing
I fission product behaviour and decontamination
1 earth quake behaviour especially of pebble bed and core internals
I impacts of graphite dust in the primary circuit
[7 He purification
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Overview on the HTR-program in Germany
Most Significant and Extensive R & D Work
Investigations experimental
anatytical m c s p
Fuel elements X X X X
PCRV X X X X
Ceramic core structure X X X X
He-technology aspects X X X
Core mechanics X X
m = material c = components s = model (various scaLes) p = prototype
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Overview on the HTR-program in Germany
Summary
Various plants developed
Two plants built and operated
All projects are accompanied by comprehensive R&D-programs
Operation results confirmed the design data
Know how is available and represents a sufficient basis for future plants
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Know how transfer to ESKOM for the PBMR
Visit of the NRC-Delegation in Germany July 23-26, 2001
Dr. Josef Sch6ning
Westinghouse Reaktor GmbH Mannheim, Germany
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Know How Transfer to ESKOM for the PBMR
Agreements with Eskom / PBMR
J MOU from April 4, 1996
9 Partner: - Eskom
9 Objective:
- German Working Group (KT GmbH / Prof. Schulten, FZJ)
- HTR GmbH
Willingness of the German Partners in principle to support Eskom in their PBMR Project and to give access to the German HTR know how
Agreement from August 8, 1996
• Partner: - Eskom
- HTR GmbH
* Objective: Supply of the SAR of the HTR-ModuLe and support Eskom's investigation into the feasibility of a HTR
I License Agreement from March 12, 1999
e Partner: - Eskom
* Objective:- HTR GmbH
Access to the HTR Technology related technical documentation as well for the HTR reactor as for the HTR Fuel as far as available in the archives. Technical assistance and consulting services, agreed on a case by case basis.
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Know How Transfer to ESKOM for the PBMR
0J Enabling Agreement for the Provision of Technical Assistance from June 2001
- PBMR (Pty) Ltd
- Westinghouse Reaktor GmbH
Objective: Scope of Technical Assistance: Layout, design, construction and calculations of reactor components and reactor systems, e.g. - reactor pressure vessel and manifold - Graphite core internals and metallic components - Disassembly equipment - fuel element detection and burn-up measurement
system - Helium fittings - Waste handling system and decontamination system - Equipment handling system - Other auxiliary reactor systems - Radiation monitoring system - Reactor protection system and post-event
instrumentation - Distributed control system
Investigations of High Temperature Reactor specific Subjects, e.g. - Disassembly and maintenance concept - Release of fission products and plate-out of solid
fission products - Impacts caused by graphite dust - Helium specific aspects (sealings, bearings, coating
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* Partner:
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Know How Transfer to ESKOM for the PBMR
Know how-transfer
1. Transfer of
documents>
2. Cooperation
1.1 definition-ESKOM, WER/HTR
1.2 selection-WER/HTR
,1.3 explanation, interpretation,WER/HTR
2.1 Consultance-WER/HTR
(derivation, correlation, adoption)
2.2 Support (single tasks)-WER/HTR
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