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CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
1
METHODS AND INSTRUMENTS FOR DOSIMETRIC MEASUREMENTS IN
MIXED NEUTRON-GAMMA RADIATION FIELDSNATALIA GOLNIK
NATIONAL CENTRE FOR NUCLEAR RESEARCH
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
MARIA REACTOR
LABORATORY FOR MIXED RADIATION DOSIMETRY
NCBJ IN OTWOCK-ŚWIERK
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
Neutron dosimetryTHE BASIC PROTECTION QUANTITY FOR IONISING RADIATION IS THE ABSORBED DOSE IN AN ORGAN OR TISSUE.
BECAUSE DIFFERENT TYPES OF RADIATIONS HAVE DIFFERENT DEGREES OF BIOLOGICAL EFFECTIVENESS ACCOUNT MUST BE TAKEN FOR RADIATION TYPE.
THE CONCEPT OF WEIGHTED DOSE SEEMS AT PRESENT THE BEST AVAILABLE.
THE PRESENT SYSTEM, RECOMMENDED BY ICRP INVOLVES A COMPLEX COMBINATION OF EFFECTIVE DOSE, THE SO CALLED „PROTECTION QUANTITY” WHICH IS USED IN LEGISLATION AND THE OPERATIONAL QUANTITIES WHICH INSTRUMENTS AND DOSEMETERS SHOULD REALISE.
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
Neutron dosimetry
AONGSIDE THE PROBLEMS OF THE COMPATIBILITY OF THE PROTECTION AND OPERATIONAL QUANTITIES THERE REMAINS THE PROBLEM OF PROVIDING DEVICES WHICH MEASURE THE OPERATIONAL QUANTITIES ACCURATELY, IN A ROUTINE AND SIMPLE WAY.
THERE REMAINS MUCH TO DO IF SUCH DEVICES ARE TO BECOME WIDELY AVAILABLE.
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
NUNC
CU
UDLT
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
1. Calibration laboratoryP. Tulik, Sz. Domański
NEUTRON SOURCES 241AM BE, 252CF, TRACEABLE TO NATIONAL PHYSICAL LABORATORY, UK, 239PU BESOURCES CAN BE EXPOSED FREE IN AIR OR IN MODIFYING FILTERS. DOSE EQUIVALENT RATE: 2 ÷1400 μSv/h.137CS GAMMA SOURCES GIVE FIELDS TRACEABLE TO POLISH COMMITTEE FOR NORMALISATION AND MEASUREMENTS; DOSE EQUIVALENT RATE OF 2 μSv/h ÷ 20 mSv/h
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
1. Calibration laboratory
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
1. Calibration laboratory
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
2. Instrument for low-level gamma and neutron monitoring
S. Pszona, A. Bantsar, K. Wincel. B. Zaremba
PHOTONS IN COMMON/AVAILABLE NEUTRON MONITORS ARE USUALLY DISCRIMINATED
NEW DESIGNED DEVICE GIVES POSSIBILITY OF REGISTRATION GAMMA AND NEUTRON COMPONENTS IN SEPARATE „WINDOWS”
0
500
1000
0 25 50 75 100 125 150
coun
ts p
er c
hann
el, a
u
channels
gammawindow
neutronwindow
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
2. Instrument for low-level gamma and neutron monitoring
FOR THERMAL AND EPITHERMAL NEUTRONS THERE IS A SIGNIFICANT CONTRIBUTION FROM SECONDARY GAMMA GENERATED BY NEUTRONS IN (N,P) REACTIONS (MONTE CARLO CALCULATIONS)
VALUE NORMALIZED TO H*(10)
1,E-02
1,E-01
1,E+00
1,E+01
1,E-08 1,E-06 1,E-04 1,E-02 1,E+00R
espo
nse t
o se
cond
ary
gam
ma,
1/n
SvNeutron energy, MeV
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
Detector
Response to gammasnSv-1
Response to neutronsnSv-1
RemarksAm Cs Cf Am-Be
NEK 240G 160* 10.5 11.6 10.3 * without
Pb filter
6.0 8.5 11.6 10.3 with Pb filter
ALMOST EQUAL RESPONSE TO GAMMA AND NEUTRONS PB FILTER GIVES POSSIBILITY TO CORRECT GAMMA ENERGY DEPENDENCECHANNELS 125-160 GIVES POSSIBILITY TO CORRECT RESPONSE >10MEV
2. Instrument for low-level gamma and neutron monitoring
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
Recombination Chamber
REM-2 recombination chamber *LARGE CHAMBER (6 KG, 1800 CM3), 25 TE ELECTRODES WITH THE DIAMETER OF 12CM;*DISTANCE BETWEEN ELECTRODES - 7 MM.*USUALLY FILLED WITH A MIXTURE OF METHANE AND NITROGEN UP TO ABOUT 1 MPA.
High-pressure, tissue-equivalent ionization chamber,
operated under conditions of initial recombination of ions
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
00
voltage
ioni
s. c
urre
nt
00
saturation current
voltage
fi
i=
0
10 100 10000.86
0.88
0.90
0.92
0.94
0.96
0.98
1.00
September 1993 March 1995 August 1995
Ion
colle
ctio
n ef
ficie
ncy
Collecting voltage, V
Ion collection effciency
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
10 100 10000.0
0.2
0.4
0.6
0.8
1.0
137Cs neutrons:
14.8 MeV 2.5 MeV 0.9 MeVIo
n co
llect
ion
effic
ienc
y
Collecting voltage, V
Dependence on radiation quality
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
10 100 10000.0
0.2
0.4
0.6
0.8
1.0
URIon
colle
ctio
n ef
ficie
ncy
Collecting voltage, V
137Cs (reference)investigated radiation
Recombination index of radiation quality
=
RnR
4 Uf1Uf1
Q
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
AMBIENT DOSE EQUIVALENT*(10)
H*(10) = D*(10) X Q
APPROXIMATION WITHIN RECOMBINATION METHODS:
H*(10) ≈ D*(10) X Q4
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
3. MONITORING SYSTEM FOR WORKPLACES
REM-2
Keithley 6517B
Interface KUSB 448B
Software
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
RESULTSRad. source D*(10) [mSv/h] Q4 H*(10) [mSv/h]
Cs-137 6,10E-02 1,00E+00 6,10E-02
Cf-252 + LiF 1,10E-02 8,29E+00 9,10E-01
Cf-252 3,2E-02 8,04E+00 2,59E-01
Cf-252 + LiF 1,11E-02 8,29E+00 9,14E-01
AmBe-241 1,54E-02 7,44E+00 1,14E-01
Cs-137 6,10E-02 1,02E+00 6,22E-02
Cs-137 6,12E-02 1,00E+00 6,12E-02
PuBe-239 1,53E-02 7,59E+00 1,16E-01
Cf-252 1,60E-02 8,23E+00 1,31E-01
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
OVERNIGHT MEASUREMENTS
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
3. Monitoring system for workplaces
T
U
Chamber
Polarization electrodes Measure
electrodes
Ground
Electrometer
E U S
-U R
i S
i R i S - i R
SRii
= ~04.0i/i1iQi~Q)10(*D)10(*H SR
S4S4
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
22
3. Monitoring system for workplaces
THE IDEA OF THE TRIPLE-MODE DETECTOR (SUMMATION MODE RAISES SENSITIVITY, DIFFERENTIAL MODE GIVES POSSIBILITY OF DIRECT MEASUREMENTS OF THE AMBIENT DOSE EQUIVALENT RATE, IN CASE OF FLUCTUATIONS OF DOSE RATE. TWO SWITCHES ARE NEEDED FOR PROPER CONFIGURATION OF POLARIZING ELECTRODES AND FOR MEASUREMENTS OF IONIZATION CURRENT.
Chamber
Polarization electrodes
UR or UM
E1
H D
or Monitor Signal
E2 US
Measure electrodes
Switch 2
Switch 1
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
4. Ionization chamber containing 10BM.A. Gryziński, K. Tymińska, M. Zielczyński
DEVELOPMENT OF A METHOD FOR DETERMINATION OF AMBIENT DOSE EQUIVALENT, H*(10), USING AN IONIZATION CHAMBER FILLED WITH BF3 TARGET
Considered solutions
• Classic recombination chamber with addition of BF3 to the filling gas;
• High-pressure chamber filled with BF3 and placed in external moderator;
• Relatively small chamber (BOR-2) in spherical moderator
• Air filled ionization chamber with 10B in material of electrodes
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
ADDITION OF BF3 (ABOUT 0,1% ) IMPROVES THE CHAMBER SENSITIVITY FOR LOW ENERGY NEUTRONS (<10 KEV) AND ONLY SLIGHTLY INFLUENCES THE ENERGY DEPENDENCE FOR FAST NEUTRONS.
Ionization chamber containing 10Bclassic REM-2 with addition of BF3 to the filling gas
Dose response calculated with MCNPX code (per 1 neutron)
1.00E-08 1.00E-07 1.00E-06 1.00E-05 1.00E-04 1.00E-03 1.00E-02 1.00E-01 1.00E+00 1.00E+01 1.00E+021.00E-04
1.00E-03
1.00E-02
1.00E-01 methane + nitrogen (5%)methane + nitrogen (5%) + boron (1%)methane + nitrogen (5%) + boron (0.075%)ICRU
Energy [MeV]
Arbi
trar
y un
its
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
THICKNESS OF THE MODERATOR, GAS PRESSURE AND POLARISING VOLTAGE SHOULD BE OPTIMISED IN ORDER TO OBTAIN SIMILAR SENSITIVITY TO H*(10) FOR NEUTRONS AND GAMMA RADIATION IN CERTAIN ENERGY RANGE
10 100 1000
20
40
60
80
100
120
i / H
*(10)
[ p
A m
Sv-1 h
]
U [ V ]
Cs
Cf
PuBe
Ionization chamber containing 10B - high pressure chamber with moderator
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
MODERATORS MADE WITH POLYETHYLENE
Ionization chamber containing 10B - high pressure chamber with moderator
90 60 45 30 0 0-dno25303540
Zależność kątowa komory
kąt [st.]
I [pA
]
Angular dependence of the chamber response
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
SATURATION CURVES OF THE REM-2 CHAMBER FILLED WITH BF3 HAVE BEEN DETERMINED IN NEUTRON AND GAMMA RADIATION FIELDS.
Ionization chamber containing 10B - high pressure chamber with moderator
Relative ion collection efficiency for 137Cs and 252Cf
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
Optimum values
• Thickness of the external moderator – ca. 3 cm
• Gas pressure – 130 kPa
• Polarising voltage – 350 V for 4 cm moderator.
Ionization chamber containing 10B high pressure chamber with moderator
0 10 20 30 40 50 60 7030
40
50
60
70
80
Response of B-chamber (Cf-252)
[mm]
[pA]
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
5. Model of recombination chamber with spectrometric properties
M. Zielczyński, N. Golnik, M.A. Gryziński, M. Maciak, K. Tymińska
PATENT APPLICATIONModel. MCNPX Visual Editor
Considered solutions
• Number of electrodes - 21;
• Made with PP-EL
• Thickness of electrodes – 10 mm;
• Electrodes covered with B4C
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
5. Model of recombination chamber with spectrometric properties
NEUTRON FLUX ON THE CHAMBER LID (0) AND CHOSEN ELECTRODES (1 21) AT 25 ‐MG/CM3 B4C LAYER THICKNESS FOR BOTH MONTE CARLO CODES.
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
5. Model of recombination chamber with multilayer moderator
NEUTRON FLUX ON THE CHAMBER LID (0) AND CHOSEN ELECTRODES (1 21) AT 600 ‐MG/CM3 B4C
LAYER THICKNESS FOR BOTH MONTE CARLO CODES.
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
5. Model of recombination chamber with multilayer moderator
NEUTRON FLUX ON THE LOWEST ELECTRODE (21) FOR VARIOUS VALUES OF THE B4C LAYER THICKNESS FOR BOTH MONTE CARLO CODES.
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
6. Passive detector with multilayer moderatorN. Golnik, K. Dworecki, M.A. Gryziński, P.Tulik, K. Tymińska
Radiation
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
6. Passive detector with multilayer moderator
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
6. Passive detector with multilayer moderator
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
1.1 Górny MTS-6 91,896 Środek MTS-6 94,50 Dół MTS-7 3,01
1.2 Górny MTS-6 124,24 Środek MTS-7 4,29 Dół MTS-7 4,02
1.3 Górny MTS-6 88,23 Środek MTS-6 96,39 Dół MTS-7 4,76
2.1 Górny MTS-6 49,88 Środek MTS-7 1,90 Dół MTS-7 2,10
2.2 Górny MTS-6 62,58 Środek MTS-7 2,31 Dół MTS-7 2,16
2.3 Górny MTS-6 44,36 Środek MTS-6 43,26 Dół MTS-7 2,34
3.1 Górny MTS-6 19,03 Środek MTS-7 0,76 Dół MTS-7 0,66
3.2 Górny MTS-6 14,83 Środek MTS-6 14,63 Dół MTS-7 0,48
3.3 Górny MTS-6 8,69 Środek MTS-7 0,28 Dół MTS-7 0,44
4.1 Górny MTS-6 14,31 Środek MTS-6 15,49 Dół MTS-7 0,55
4.2 Górny MTS-6 11,13 Środek MTS-7 0,46 Dół MTS-7 0,34
4.3 Górny MTS-6 6,32 Środek MTS-6 7,24 Dół MTS-7 0,16
5.1 Górny MTS-6 17,48 Środek MTS-6 16,57 Dół MTS-7 0,89
5.2 Górny MTS-6 19,16 Środek MTS-7 1,10 Dół MTS-7 0,74
5.3 Górny MTS-6 11,11 Środek - Dół MTS-7 0,61
6.1 Górny MTS-6 21,77 Środek - Dół MTS-7 2,24
6.2 Górny MTS-6 76,44 Środek - Dół MTS-7 2,73
6.3 Górny MTS-6 58,60 Środek - Dół MTS-7 3,01
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
7. Accident dosimetry
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
7. Accident dosimetry
NO. AMOUNT TITLE1 1 Power Output Coating2 1 Power Output3 1 Power Output Spacer4 1 Casing5 2 Capacitor 4.7nF M6 1 External Electrode7 1 Internal Electrode8 1 Measuring Output Spacer9 1 Grounding Output
10 1 Measuring Output11 1 Nut
PARTS LIST CAPACITORS AS A DETECTOR
CENTRAL LABORATORY FOR
RADIOLOGICAL PROTECTION
IAEA PROJECT RER/9/117 Regional Workshop on Regulatory Control of Radioactive Discharges to the Environment
17-21 June 2013, Warsaw, Poland
DEVELOPMENT OF NUCLEAR SAFETY AND RADIOLOGICAL PROTECTION METHODS FOR THE NUCLEAR POWER ENGINEERING’S CURRENT AND FUTURE NEEDS
Polish National Centre for Research and Development (NCBiR)
THANK YOU FOR YOUR ATTENTION
WE WILL SHOW MUCH MORE IN NEXT YEAR