1944-20 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for...

1944-20

Joint ICTP-IAEA Workshop on Nuclear Reaction Data for AdvancedReactor Technologies

BORELLA Alessandro

19 - 30 May 2008

Institute For Reference Materials and MeasurmentsEC JRC IRMMRetiesweg 111B-2440 Geel

BELGIUM

Cross Section Measurements and Uncertainties of Cross Section Data.

Monte Carlo methodsEUROPEAN COMMISSION

Workshop On Nuclear Data for Advanced Reactor Technologies, ICTP 22-05-2008, A. Borella

Simple Monte Carlo Example

Evaluate G=jg(x)dx, with g(x) = V i -

Simulation approach:"darts game"For k = 1,...,N: choose i ^ yk randomly in (0r1):

it x^+v= < 1 r tally a "hit"

number of hitsG = [area under curve] - (1 1) N

EUROPEAN COMMISSION


Monte Carlo approach to particle transport- Random Numbers are generated to solve particle transport- Vs. deterministic codes

- Relies on:• Physics and particle transport equations• Data (cross sections) for the various process

• Where data are not available relies on models

- The history are tracked by generating random number (RN):so-called "random walks"

- According to the value of the RN, the XS and the physics, the particlefate will be different

- The source particle and possible secondary particles are tracked inthe medium according to the geometry and composition

- Quantities of interested (the so-called tallies) are computed

- More info and documentation: http://mcnp-green.lanl.gov/

MCNP/MCNPXEUROPEAN COMMISSION


MCNP is a code developed by LANL to simulatethe transport of neutrons, gamma rays andelectrons by the Monte Carlo method. Itsimulates a coupled transport, i.e., it alsoaccounts for transport of secondary particleresulting the interaction of primary particles.

MCNPX extends the capacilties of MCNP to otherparticles (e.g. charged particles, heavy ions,pions etc.)

Jnli Problems that can be solved *-ttiEUROPEAN COMMISSION ,,,,,.,J,,L

Malerials and Measure me nlsWorkshop On Nuclear Data for Advanced Reactor Technologies, ICTP 22-05-2008, A. Borella

Problems that can be solved/Fields of application* Reactor calculations

BurnupCriticality

* Medical applicationRadiography

* Detectore.g. C6D6

* High energy physics (MCNPX)* Space applications

EUROPEAN COMMISSIONMCNP users groups


Application

Medical (BNC T. proton therapy, etc.)

Spacecraft, Cosmic Rays, SEE. propulsion

Detectors, experiment1;. Threat Reduction

ATW, .ADS. Energy Amplifier:

Fuel cycles, beginning to end. including storage

Accelerator Shielding ami Health Physics

Theoretical Physics

Neutron Production for Scattering

Isotope Production

Radiography

MCNFXMCNP code development

Homeland Security

Material*; stadies (IFMIF)

Radioactive Ion Benin1;

Irradiation Facilities

Neutrino Targets

Light Source1;, electron machines

U Groups

50

4:

39

3"

32

28

23

21

14

12

11

ID

6

•*

4

4

3

Percent

1?

12

11

11

9

8

-r

6

4

4

3

3

i

1

1

1

1

EUROPEAN COMMISSION


Examples- Gamma ray transport- Neutron transport

Structure of the input file- Cell- Surfaces- Materials (XS)- Source definition- Tally- Additional options

Output files- Binary- Out file- Other files (mctal)

Tallies examplesEUROPEAN COMMISSION


F l ; Surface Current

F2: S u rface F Luence

FA: CellFLuence

F5: Detector FLuenoe

Ene igy Deposit ion

F7: Fission Energy Deposition

FS: Pulse Height

JRCEUROPEAN COMMISSION

Example 1 - gamma transport mWorkshop On Nuclear Data for Advanced Reactor Technologies, ICTP 22-05-2008, A. Borella

Institute for ReferenceMaterials and Mea s u re me r>ls

Point source in (0,0,0)Isotropic source

Ey = 1 MeV

Response in a sphereDeposited energyRin=10 cm Rout=15 cm

BaF

EUROPEAN COMMISSIONExample 1 - gamma transport m

Institute for Reference.Marerials and Measurenicnls



Example 1 - gamma transport mInstitute for Reference.Marerials and Measurenicnls


EUROPEAN COMMISSION


example 1: g source response for c6d6cc —1 02 13 0c

-1.0020-20 10-10

imp:n,p,e=0imp:n,p,e=1imp:n,p,e=1

$ univers$ univers$ univers

cc surface definitions for PM10 so 10.0 $ global univers20 so 15.0 $ global universc

cMODE P Ecc ZZAAA AT1 ZZAAA AT2M1 6012 0.5 1002 0.496 1001 0.004 $ c6d6cSDEF ERG=1 PAR=2 POS=0 0 0ccF8 : P E 2E8' ' 0 999I 1.0 $ 1 keV/bincNPS 1e5

EUROPEAN COMMISSIONExample 1 - c6d6 result


EUROPEAN COMMISSIONExample 1 - BaF2 result



Example 3 - neutron transport mWorkshop On Nuclear Data for Advanced Reactor Technologies, ICTP 22-05-2008, A. Borella



En = 0.1-1 MeV

Flux in a sphere vs EFlux through surfacesRin=10 cm Rout=10.5 cm

Co+Ag

cp(E) spectrum ?

EUROPEAN COMMISSION


example 1: n transport response for co+ag

c —1 02 13 04 0

-8.9030-20 10-1020 -30

imp:n,p,e=0imp:n,p,e=1imp:n,p,e=1

imp:n,p,e=1

$ univers$ univers$ univers

$ univers

c surface definitions for PM10 so 10.0 $ global univers20 so 10.5 $ global univers30 so 100.0

cMODE NMl 27059 1.0 $ CocSDEF ERG=D1 PAR=1 POS=0 0 0SI1 H .1 1SP1 0 1cF12:n 30 $surface flux 2T12 1.0e00 999I 1.0e03 $ 10 ns binscNPS 1e07


Example 3 - flux attenuation by co+agWorkshop On Nuclear Data for Advanced Reactor Technologies, ICTP 22-05-2008, A. Borella

1.00E-08 -

8.00E-09 -

6.00E-09 --

4.00E-09 --

2.00E-09 -

0.00E+00

•ArmmInstitute for Reference.Marerials and Measurenicnls

1.00E-04 2.00E-04 3.00E-04 4.00E-04 5.00E-04 6.00E-04 7.00E-04 8.00E-04 9.00E-04 1.00E-03

En / MeV


Example 2 - neutron transport mWorkshop On Nuclear Data for Advanced Reactor Technologies, ICTP 22-05-2008, A. Borella



En = 1 MeV

Flux in a sphere vs EFlux through surfacesRin=10 cm Rout=50 cm

H2O

EUROPEAN COMMISSIONExample 2 - flux through surfaces m

Institute tor ReferenceMaterials and Measurement


100000

10000

1000

100

10

1 n

0.1 n

0.01 n

c^ 1E-3 -;

^ 1E-4 -j

1E-5

1E-6

1E-7

1E-8

1E-9

CD

1E-101E

i i i i i i i i i

10 1E-9 1E-8 1E-7 1E-6 1E-5 1E-4 1E-3 0.01 0.1• • • • I

10

E /MeVn

EUROPEAN COMMISSIONExample 2 - flux in volumes


100000

10000

1000

100

0

. O

1

0.1

0.01

1E-3

1E-4

1E-5

1E-6

OCELL 2

i i i ^

1E-10 1E-9 1E-8 1E-7 1E-6 1E-5 1E-4 1E-3 0.01 0.1""I10

E /MeVn

1944-20 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for...

Documents

Transcript of 1944-20 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for...