1. JOINT INSTITUTE
FOR NUCLEAR RESEARCH
Simulation of spallation and transmutation minor actinides in fast subcritical reactor
apprentice: Przemysław Stanisław Stanisz
supervisor: Aleksander Polański (LIT)
DUBNA

2. Models and Codes Used for Simulations
MCNP (Monte Carlo N-Particle code)
is developed by Los Alamos National Lab (LANL) to simulate the transport of neutrons, gamma rays and electrons by the Monte Carlo method. It simulates a coupled transport, i.e., it also accounts for transport of secondary particle resulting the interaction of primary particles.
MCNPX (Monte Carlo N-Particle eXtended)
extends the capacilties of MCNP to other particles (e.g. charged particles, heavy ions, pions etc.) 
CINDER90
code and library to developed for the description of nuclide inventories produced in a wide range of radiation environments

3. The Spallation Proces Fast Direct Process: Compound Nuclei:
- Intra-Nuclear Cascade (nucleon-nucleon collisions)
Compound Nuclei:
- Evaporation
(mostly neutrons)
- High-Energy Fissions

4. Spallation Neutron Yield
Spallation Neutron Yield (mean multiplicity of emitted neutrons)
The number of emitted neutrons varies as a function of the target nuclei and the energy of the incident particle
L. Pienkowski, F. Goldenbaum, D. Hilscher, U. Jahnke
Neutron multiplicity distributions for 1.94 to 5 GeV/c proton-, antiproton-, pion-, kaon-,
and deuteron-induced spallation reactions on thin and thick targets

5. Spallation Neutron Spectrum
The spectrum of spallation neutrons evaporated from an excited heavy nucleus bombarded by high energy particles is similar to the fission neutron spectrum but shifts a little to higher energy

6. Spallation Product Distribution
The spallation product distribution varies as a function of the target material and incident proton energy. It has a very characteristic shape:

7. ADS geometry model Characteristics Destription
MeV 1000 protons, beam power
1,16MW
Thermal fission power
100MW
Diameter of the core.
520 [mm]
Height of a fuel active part
630 [mm]
Radius of lead reflector
Number of the fuel elements in assembles 18
Number of fuel assembles
133
Maximal gain factor
Keff=0,97
Heat-carrier
helium
Radius of concrete shielding
190 [cm]
Max neutron flux
6.64E15 [cm2/s]
ADS geometry model

8. FAST Reactor geometry model
Characteristics
Destription
Thermal fission power
100MW
Diameter of the core.
520 [mm]
Height of a fuel active part
780 [mm]
Radius of lead reflector
520 mm
Number of the fuel elements in assembles 18
Number of fuel assembles
153
Maximal gain factor
Keff=1,1
Heat-carrier
helium
Radius of concrete shielding
190 cm
Max neutron flux
6.64E15 [cm2/s]

9. Reactivity change in burnup cycle

10. ADS and Fast Reactor Neutron Spectra

11. Mass evolution of Plutonium

12. Mass evolution of Minor Actinide (MA)

13. Thank you
for attention