Overview on the HTR-program in Germany · 71 BBC line -AVR, THTR, HTR 500, HTR 100, GHR, HHT, PNP 7...

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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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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

Z01 037

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(LWR)

WM-Modul

Westinghouse


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


"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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S01_087


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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THTR Longitudinal Section

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THTR Dry Cooling Tower

I4 I

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THTR Fuel Handling System

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THTR

Prestressed Concrete Reactor Vessel

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(* Westinghouse , BNFL

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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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HTR 500 Longitudinal Section

Reactor protection building

30,0 48,0 42,5 12,5 66,0

199,0

SOl1095

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Overview on the HTR-program in

HTR Modul Cross Section

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I

Germany


HTR Modul Cross Section

Sol 100

Reactor pressure vessel Steam generator vessel Connecting pipe Primary coolant blower

5 6 7 8

Primary shielding Full protection wall Liner cooLer Reactor building extension

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GHR 10 Gas Cooled Heating Reactor

Prestressed concrete vessel

Graphite reflector

Core H;

S01_096

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GHR 10 Heat Flow Diagram

Inside reactor vessel Outside reactor vessel

S01 097

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GHR 10 Longitudinal Section

MAINTENANCE HALL

"DECAY HEAT REMOVAL SYSTEM

FACTOR PRESSURE VESSEL

22,20 1Sal 098

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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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Scope and Depth of R & D

Core physics N and hydraulics

Model tests for . extrapolation laws

He-technology effects

Materials

0

8E

7:$

Tests of single elements

Prototype tests

Acceptance tests

Commissioning test

Z01035

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Design of reactor

components

21

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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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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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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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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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71

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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

Fol0l 051 -E- [07101 ] 1

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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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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

etc.)Fol1l 1 01 -E [07/101 3i

(* )Westinghouse , BNFL

* Partner:

G

^


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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Overview on the HTR-program in Germany · 71 BBC line -AVR, THTR, HTR 500, HTR 100, GHR, HHT, PNP 7...

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