General
To continue the
tradition of the previous years, and to fully utilise the benefits of
international co-operation
and to promote the knowledge in nuclear engineering a 21 day course is being
organised starting at 2 September 2009.
The language of
the course is English. The main emphasis of the course is to perform reactor
physics experiments on three different research- and training reactors
in three different cities (
The Quality
Assurance Committee of the European Nuclear Education Network (ENEN)
Association has
recommended this course to the ENEN General Assembly to entitle with the quality
label “International ENEN Exchange Course”, which means that the quality
control of the ENEN Association assures that the acquired knowledge of the
participants will fulfil the requirements of the European Nuclear Education and
fits in the ECTS system.
Participation
The course is
open to the following categories of persons:
·
Undergraduate, graduate and PhD students;
·
Young professionals working in different nuclear installations.
Basic knowledge
of reactor physics theory is requested. This knowledge has to be attested by a professor
of the student’s home university or by a professional leading person in the
nuclear installation where the participant is working in.
The number of
participants is limited to 10. The application is subject of a selection procedure,
and may be refused, if the course is already fully booked, or if the selection committee
decides so, due to any reason.
The application
deadline is 31st of May 2009 (via email). The selection
will be made till
15th of June 2009. Each
applicant will be informed about his/her acceptance and about the details of the
payment (see below). The deadline for the payment is
The candidates
should fill in the Application Form (Appendix I), provide the necessary
attachments, and send via
email them to the following address:
Dr. Ján Haščík, Department of
Nuclear Physics and Technology
Ilkovičova 3; 812 19 Bratislava;
Slovakia.
Phone: +421-2-602-91-289;
Fax: +421-2-654-27-207;
e-mail: jan.hascik@stuba.sk.
Cost of the
course:
The fee of the
21 day course is € 2 500. According to the ENEN Association policy students of ENEN member
universities get a reduction € 500.
PAYMENT DETAILS
Bank name: Poštová banka, a.s.
Bank address: Prievozská 2/B, 824 64
Account name: Slovenská spektroskopická
spoločnosť
Account number: 0020096353
IBAN: SK31 6500 0000 0000 2009 6353
BIC/SWIFT: POBNSKBA
Payment description: EWC 2009 - first name, family name
Deadline for
payment of the EWC 2009 participation fee is
The cost of the
course includes:
·
the tuition fee (lectures, laboratory exercises)
·
utilization of 3 research reactors;
·
participation at a technical tour to a NPP and radwaste
treatment centre;
·
the textbooks;
·
the welcome dinner;
·
the farewell
dinner.
Not included
are:
a)
·
the accommodation during the course;
·
the transport tickets between the four countries during the course;
·
the transport tickets inside the cities from the accommodation place to
the experimental facilities and back;
b)
·
the travel to the “starting place” (
·
the cost of the meals (with the exception of the welcome and farewell
dinner);
·
personal insurances;
·
visa (if necessary).
For arranging
the not-included items there are two different options:
1.
All additional costs (accommodation, travel, meals
etc.) during the course can be arranged and paid individually by the
participants. The organisers are ready to assist in finding and reserving
accommodation at moderate price in the different cities when required timely in
advance.
2.
A “package” is offered for € 1500, which includes
accommodation cost (about € 55/night
comfort level), transport tickets between the four countries during the
course and transfer costs inside the cities (category “a” in the list above).
The organisers will arrange the reservations and payment of the accommodation
and of the travel tickets for the participants choosing this option. This is a
cheap and simple solution. However, this still does not include category “b”,
i.e. meals, personal insurances, visa (if necessary at all). These latter
should be paid and arranged individually in any case.
Important note: The organizers
of the course do not accept liability for the payment of any cost or
compensation that may arise from damage to or loss of personal property, or from
illness, injury, disability or death of a participant while he/she is travelling
to and from or attending the course. The participants are well advised to
take insurance against these risks.
DETAILED
DESCRIPTION OF THE COURSE
1. Overall
time-table
The
participants work and travel together. On the first week they follow the
preparatory theoretical courses in
September 2
– 22, 2009 (21 day)
|
day |
date |
Place |
date |
place |
date |
place |
|
Wed |
2.9. |
arrival + free day |
9.9. |
|
16.9. |
travel |
|
Thu |
3.9. |
|
10.9. |
self study + travel |
17.9. |
|
|
Fri |
4.9. |
NPP J. Bohunice |
11.9. |
|
18.9. |
|
|
Sat |
5.9. |
|
12.9. |
self study |
19.9. |
|
|
Sun |
6.9. |
travel + free day |
13.9. |
free day |
20.9. |
|
|
Mon |
7.9. |
|
14.9. |
|
21.9. |
|
|
Tue |
8.9. |
|
15.9. |
|
22.9. |
|
2.
The theoretical courses:
The theoretical lectures will be
held in the lecture halls and laboratories of the Slovak University of
Technology, Ilkovicova 3,
2.1 Nuclear Safety
(2 hours lecture, Prof. Dr. V. Slugen
[
· General information about nuclear
safety
· Defence in depth (accident
prevention and mitigation)
· Safety culture
· Legislative rules
· Physical protection
· Safeguards at research reactors
· Application of nuclear safety at
research reactors
· Emergency preparedness
2.2 Survey of research reactors and
associated systems
(2 hours lecture, Dr. M. Villa [
Survey of
research reactors’ use (overview, reactor utilisation in physics, chemistry,
medicine, biology, training purposes and industrial applications)
Selected
systems and components
·
Fuel
elements for research reactors
·
Safety
and control systems (including control rod and neutron detectors)
·
Cooling
and ventilation systems
·
Experimental
facilities
2.3 Instrumentation for nuclear
measurements
(2 hours lecture, Prof. Dr. M. Miglierini [Bratislava])
· Principles of detection.
· Gas-filled detectors. Scintillation
detectors. Semiconductor detectors.
· Neutron detectors
· Single-channel analyser,
multichannel analyser, multiscaler mode
2.4 Data evaluation techniques (related to the
practical exercises)
(2 hours lecture, Prof. Dr. Sz. Czifrus [
· Principles of parameter estimation
· Maximum likelihood method, the
method of least squares, some illustrative examples
· Solution of the least squares
equations
· Statistical properties of the
estimated parameters (expectation value, standard deviation)
· Confidence intervals
· Goodness of fit tests
2.5 Radiation protection and dosimetry
(2 hours lecture, Dr. R. Hinca [
2.6 Methods of reactivity measurements
(2 hours lecture, Prof. Dr. J. Hascik [
· Introduction into the measurements
of reactivity, definition and units
· Source jerk method
· Inverse count rate
· Rod drop method
· Inverse kinetics
· Positive period method
2.7 Laboratory
practices related to reactor physics and nuclear measuring techniques
(2 x 2 hours laboratory
exercises, 2.7a Prof. Dr. J. Hascik,& Prof. Dr.
V. Slugen, 2.7b Prof. Dr. M. Miglierini,
& Dr. R. Hinca [
2.7.a Determination of Fermi age
2.7.b Gamma spectrometry measurements
Timetable
of the Bratislava-part: 2. - 6.9.2009
|
2nd September (Wednesday) |
14:00 - |
Arrival, occupying accommodation |
|
18:00-20:00 |
Opening ceremony welcome buffet (FEI STU, B-Klub, block A,
ground floor) |
|
|
3rd September (Thursday) |
08:30 – 08:45 |
Organisational matters |
|
08:45 – 10:15 |
Lecture 2.3 |
|
|
10:30 – 12:00 |
Lecture 2.2 |
|
|
12:00 – 14:00 |
Lunch break |
|
|
14:00 – 15:30 |
Lecture 2.4 |
|
|
15:45 – 17:15 |
Lecture 2.5 |
|
|
4th September (Friday) |
07:00 – 16:45 |
Technical tour to Nuclear & Decommissioning Company j.s.c. at Jaslovské Bohunice
visit to NPP V1 and to a Radwaste Treatment Centre |
|
5th September
(Saturday) |
08:45 – 10:15 |
Lecture 2.1 |
|
10:15 – 12:00 |
Lecture 2.6 |
|
|
12:00 – 14:00 |
Lunch break |
|
|
14:00 – 15:30 |
Exercises 2.7a group A; 2.7b
group B |
|
|
15:45 – 17:15 |
Exercises 2.7b group A; 2.7a group B |
|
|
6th September (Sunday) |
|
Travel to |
3. Reactor
experiments in
The reactor
experiments will be performed at the 100 kW training reactor of the Institute
of Nuclear Techniques (INT) of the Budapest University of Technology and
Economics (BME) (
3.1
Determination of the distribution and of the absolute value of the thermal
neutron flux by activation method
The experiment
involves the determination of the relative distribution of the thermal neutron flux
along a vertical axis of the active core, furthermore, determination of the absolute
value of the thermal neutron flux at the center of the reactor.
3.2 Measurement
of delayed neutron parameters and determination of uranium concentration
Half lives and
relative intensities of some delayed neutron groups are determined. In the second
part of the exercise the 235U concentration of a depleted uranium
sample is estimated by comparing the delayed neutron intensities in the sample
of interest and in uranium standard.
3.3 Measurement
of void coefficient and the reactivity worth of neutron absorbers
The void
coefficient of the reactivity and the reactivity worth of neutron absorber is studied, when moving a void and a neutron absorber
respectively along a vertical axis in the active core.
4. Reactor
experiments in
The reactor
experiments will be performed at the TRIGA Reactor Facility of the Atominstitut der Österreichischen Universitäten (
4.1 Fission
chambers (FC), compensated ionisation chambers (CIC), self-powered (SP) detectors
These detectors
will be exposed to various level of neutron fluxes and
their sensitivity and time behaviour will be determined. For FC and CIC the
discrimination between the neutron and gamma signal will be demonstrated. For
SP the signal time behaviour will be shown after reactor shut down.
4.2 Reactor
power calibration and temperature coefficient of reactivity
The reactor is
operated at 10 W, rod positions, water- and fuel temperature is noted, then the
reactor power is raised to 100 kW, again the values are noted. From the
difference in rod position and fuel temperature the fuel temperature
coefficient can be determined. Then the reactor is operated for 90 min only
with convection cooling and the increase of water temperature is monitored.
Comparing the temperature increase with the value from a previous calibration
the thermal reactor power can be determined.
4.3 Critical
experiment
Ten fuel
elements are removed from the reactor core and consecutively reloaded. The neutron
count rate is measured after each step. At each step measurements are performed
with all control rods up and then down. Criticality is reached with all control
rods up after reloading of five fuel elements.
4.4
Demonstration of a prompt critical power excursion (requires only a
short time)
Due to the
strong negative temperature coefficient of reactivity TRIGA reactors allow prompt
critical excursion to 1000 times the normal power mode without any damage to the
core. This is demonstrated using a pneumatic rod, which is removed promptly
from the critical core. Typical power levels of 250 to 300 MW are reached for a
time period of about 40 ms.
5. Reactor
experiments in
The reactor
experiments will be performed at the research reactor facility of the
5.1 Measurements
of reactivity by various methods
Reactivity
measurements in the subcritical state by “source jerk” method (using quickly moveable
external neutron source), reactivity measurements in the supercritical reactor
by “positive period” method, “rod drop” method (control rod worth measurement)
5.2 Study of
nuclear reactor dynamics
Mathematical
model of the research reactor dynamics, study of the reactor response to the negative
/ positive periodical reactivity change, study of the influence of the bubbly
boiling to the VR-1 reactor operation, simulation of the selected operating
conditions of a WWER-type power reactor: approaching to the critical state with
modeling of the dilution of boric-acid concentration and change the operating
group of the control rods
5.3 Digital
control and safety systems of the research reactors and reactor operation
Digital control
and safety systems based on microprocessors, the operational power measurement and
independent power protection systems, the control system and the human-machine
interface (control desk), the start-up of the reactor, the operation in manual and
automatic mode, the changes of the power (increasing, decreasing), the shutdown
of the reactor because of various reasons can be demonstrated, various
inspections and checks of the digital control and safety system.