26

TH

RROG ANNUAL MEETING

14

th

to 17

th

May 2014 Atominstitut, Vienna, Austria

• • • • • •

History of the TRIGA Mark II Reactor Vienna

250 kW TRIGA Mark II reactor at the Atominstitut in Vienna critical since March 7 th 1962 Initially started up with 66 TRIGA fuel elements type 102 (Al-cladding, LEU) Following years elements of the type 104 (SST-cladding, LEU) were purchased In 1972 fuel elements of the type 110 (SST-cladding, 70% enriched) where acquired and placed in the core The last 8 fresh fuel elements were acquired from the Triga reactor in Heidelberg Core conversion in November 2012

Main technical Data of the TRIGA Mark-II Reactor Vienna (1)

1. Reactor

Fuel-Moderator Material Uranium enrichment Active core volume Core loading Amount of U-235 per fuel element Reflector Reactor control 8.5 wt% uranium 89.9 wt% zirconium 1.6 wt% hydrogen 19.8 % and 70% uranium-235 49.5 cm diameter 38.1 cm high 76 fuel elements, approx. 38 grams graphite 2 motordriven control rods 1 pneumatic control rod material prompt negative temperature coefficient of the fuel

Main technical Data of the TRIGA Mark-II Reactor Vienna (2)

2. Steady state reactor operation mode

Maximum thermal power Maximum thermal neutron flux density Maximum fuel temperature Maximum primary water temperature

3. Transient reactor operation mode

peak, power thermal Integrated energy production total duration of power pulse minimum reactor period maximum fuel temperature 250 kW 1x10 13 cm -2 s -1 220 ° C 35 ° C 250 MW 12 MWs 40 ms 10 ms 360 ° C

Specification of Fuel Elements

Fuel moderator material H/Zr-ratio Uranium content [wt%] Enrichment [%] Diameter [mm] Length [cm] Poisoning Graphite reflector Porosity Diameter [mm] Length [cm] Fuel cladding Material Wall thickness [mm] Overall dimensions Outer diameter [mm] Length [cm] Type 102 1.0 8.5 20 35.8 35.6 SmO 3 -disks 20 35.8 10.2 Al-1100 F 0.76 37.5 72.06 Type 104 1.65 8.5 20 36.3 38.1 none 20 36.3 8.73 304 SS 0.51 37.5 72.06 Type 110 (FLIP) 1.65 8.5 70 36.3 38.1 Er with 1.6 w/o 20 36.3 8.81 304 SS 0.51 37.5 72.06

Fuel Inventory as per 01.01.2014

Date 05.12.61 07.07.62 19.02.65 02.08.66 21.10.68 19.10.72 02.12.80 09.08.82 15.02.83 21.08.87 19.10.88 01.02.90 14.12.00 30.10.2012 07.11.2012 total: Number of FE + 66 - 2 (retour) + 2 + 3 + 3 + 9 + 1 + 3 + 2 + 3 + 3 + 3 + 8 + 77 - 91 (retour) 90 Type Al, 20% Al, 20% Al, 20% SST, 20% SST, 20% SST, 70% SST, 20% SST, 20% SST, 20% SST, 20% SST, 20% SST, 20% SST, 20% SST, 20% SST 20% and 70%, Al 20% Remarks 2 instrumented fuel elements 1 instrumented fuel element 5284 TCE 1 instrumented fuel element 8257 TCE 2 instrumented fuel elements 8730, 8731 TCE 75 FE from Musashi and 2 FE from Cornell 3 instrumented fuel elements

Fuel Element Situation as per 01.01.2014

Number of FE 76 9 5 - 1/3 total: 90 Location core storage pits fresh fuel storage spent fuel storage hot storage facility Al - - - - 1/3 Cladding SST 76 9 5 - - 1/3 90 Enrichment 76 FE 20% 9 FE 20% 20% 20% Remarks 2 instr. FE 1 instr. FE cut into 3 pieces Total uranium weight: 17 287.19 g U-235 weight: 3 436.33 g

• • • • •

Ongoing Activities (1)

Reactor was in 2013 for more than 200 days in operation 6 weeks practical courses for the Vienna University of Technology, 2 weeks for the University of Manchester and 3 weeks for the IAEA Replacement of the old I&C system is financed by the Vienna University of Technology From 3 different vendors; Skoda, Invap and GA, the Skoda company located in Pilsen was chosen as they offered the cheapest price fulfilling all the specifications mentioned in the call for tender. The 1 st coordination meeting took place on the 21. February 2014. The replacement of the old I&C system and the installation of the new one is scheduled for the summer 2015.

Ongoing Activities (2)

• • • One new deputy reactor manager and one new nuclear security officer was put in place in 2013 Due to the European law a periodic safety review of the installation has to be performed till the end of 2014 A detailed inspection of the facility together with the governmental expert Dr. Gabriele Hampel took place, as an outcome of this inspection the main nuclear parts have to be replaced by new components – New primary circuit (pumps, pipes and heat exchanger) – New secondary circuit (pumps and pipes) – – New purification pump New ventilation system of the reactor hall (motors and fittings) – Several new auxiliary systems (electrical installation, lamps, etc..)

Operational History for 2013

January February March April May June July August September October November December 2013 2013 2013 2013 2013 2013 2013 2013 2013 2013 2013 2013 14.04

28.70

26.19

26.44

8.83

18.28

18.66

28.70

24.77

28.11

22.64

12.17

MWh MWh MWh MWh MWh MWh MWh MWh MWh MWh MWh MWh Total Reactor in operation 257.53

213 MWh days

Operation Performance 2008 to 2013

NUMBER OF NUMBER OF NUMBER DAYS DAYS AT OF AT DAYS NUMBER AT OF NUMBER DAYS OF NUMBER AT DAYS OF OF POWER  NUMBER POWER AT AT OF (_________ ) UNSCHEDUL UNSCHEDUL DAYS ) SHUTDOWN (_________ UNSCHEDUL ED (________) ) SHUTDOWN SHUTDOWN  100  (________)  100  (________)  100 

Performance Indicators for 2013 (1)

Availability A1 [%]

99.53

A2 [%]

58.36

Unscheduled Shutdowns B1 [1]

1

B2 [1]

0

A1



Number Number of days at power



of days Number at power of days unschedule d shutdown



100 A2



Number of days 365 at power



100 B1: Number of unplanned reactor shutdowns initiated by reactor protection system or manual intervention B2: Number of unplanned reactor shutdowns initiated by experiments under irradiation

Performance Indicators for 2013 (2)

Radiation Dose Exposure D1a D1b D1c D2a D2b D2c [mSv] [Persons] [mSv/Person] [mSv] [Persons] [mSv/Person]

4.28

4 1.07

18.53

18 1.03

D1a: Collective radiation dose to reactor operations staff D1b: Number of reactor operations staff D1c: D1a / D1b D2a: Collective radiation dose to all staff from reactor related work D2b: Total number of staff involved D2c: D2a / D2b

Performance Indicators for 2013 (3)

E1 [TBq]

0.66

Radioactivity released E2 [TBq]

n.a.

E3 [MBq] E4 [MBq]

0.024 < 0.037*

* below the limit of detection E1: Rare gas released to atmosphere (Ar-41) E2: Tritium released to atmosphere E3: Tritiated water discharged E4: Iodine released to atmosphere

•

Staff

Central facility “Reactor” – 1 reactor manager – 1 deputy reactor manager – 2 reactor operators • Central facility “Nuclear Safety” – 1 nuclear security officer – 1 deputy security officer • Central facility “Radiation Protection” – 1 radiation protection officer – 1 deputy radiation protection officer – 1 technician

Training programme for personnel

• • • • • • Reactor manager Deputy reactor manager Nuclear security officer Radiation protection officer - Every 5 years minimum - Minimum 40 hours - Conferences Reactor operators Radiation protection technicians - Every 5 years minimum - Minimum 8 hours - Conferences

Qualification of the operators

• • • • Since 1962 the Atominstitut operates the TRIGA Mark II reactor with two operators. The last two came in the year 1975 and 1978.

One operator was trained in a special course at a technical High School for nuclear engineering dedicated for future operators for the Austrian NPP Zwentendorf.

As most of the lectures at that time were held at the Atominstitut he moved to our facility as a new operator was needed due to retirement.

The second operator was trained directly in our facility as the as the NPP was not put into operation and the High school was already closed.

Retraining of the operators (1)

• • The retraining of the operators is split into two parts. One part is the participation in the different practical courses carried out at the Atominstitut. In all this courses the operators work closely together either with operators of other nuclear facilities or students from different universities. During this courses practical skills are trained again and different questions concerning reactor related themes are discussed. Safety issues of different nuclear facilities are discussed and the different practices are compared. As we are a small group every interesting topic is discussed together with the operators.

Retraining of the operators (2)

• In addition to this courses excursions to other nuclear facilities are organized like: – TRIGA Munich – RR Seibersdorf – NPP Bohunice – NPP Temelin – NPP Dukovany – NPP Mochovce – NPP Zwentendorf – TU Bratislava – TRIGA Lubjana – TRIGA Rom – TRIGA Pavia

Radiation Protection Staff

• • • 3 Persons in the radiation protection departement Head of department and 2 radiation physicists Deputies in each research area • Advanced training for the radiation protection staff - Every 5 years minimum - Minimum 8 hours - Conferences

Radiation Protection Courses

• • • • • Individual courses are planed and held by the radiation protection staff Handling sealed sources Handling unsealed radiactive material Contamination – decontamination Dose and activity calculations • • • • Internal courses Courses for staff of the institute Once a year Theoretical and practical topics • • • • External courses In cooperation with companies and authorities For beginners and experts in radiation protection Also theoretical and practical topics

Safety Evaluation

• Document: Safety Analysis – analysing risks

Initiating event Explosion Fire … Technical countermeasures

Ventilation, burnable liquids in fire resistant cabinets Ventilation, burnable liquids in fire resistant cabinets, hand held fire extinguisher, fire detectors

… Organisational procedures

Automatic fire detection system, Emergency plan Automatic fire detection system, Emergency plan

… Risk

Low Low

…

Emergency Plans

• • Internal alarms: Responsibility: – Reactor Manager – Radiation Protection Officer – Nuclear Safety Officer • • External alarms: Responsibility: – National Authorities

Internal alarm Alarm at the security office Handling the event External alarm Documentation and accident review

• • • •

Present Situation in Vienna

Replacement of the old I&C system is in progress Replacement of primary circuit, secondary circuit, purification circuit and the reactor ventilation is in progress Estimation of the decommission costs together with Austrian research center in Seibersdorf Increasing demand on practical courses