1. Fusion Neutronics, Nuclear Data, Design & Analyses
Forschungszentrum Karlsruhe
Technik und Umwelt
Fusion Neutronics, Nuclear Data, Design & Analyses
- Overview of FZK Activities -
U. Fischer
Association FZK-Euratom
Forschungszentrum Karlsruhe, Germany
IEA International Workshop on Fusion Neutronics, Baden-Baden, Germany, 18 October 2001

2. Overview Nuclear Blanket Design Neutronics Research & Development
Fusion power reactor & ITER/next step
Neutronics Research & Development
MC sensitivity/uncertainty computational technique
Code system for 3D shut-down dose rate calculations
Nuclear Experiments & Analyses
ITER shut-down dose rate experiment (FNG)
Cyclotron irradiation experiment on tungsten
IFMIF Intense Neutron Source
Neutronics, nuclear data, D-Li source term
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

3. Blanket Design & Development
European Fusion Technology Programme
Helium Cooled Pebble Bed (HCPB) Blanket
Water Cooled Lithium Lithium-Lead (WCLL) Blanket
Fusion Power Reactor
Power Plant Conceptual Study (PPCS)
2001: Near-term concepts (HCPB, WCLL)
2002: Advanced blanket concepts
ITER/”Next Step”
HCPB test blanket modules
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

4. ITER Test Blanket Module
HCPB test blanket modules in ITER-FEAT (MCNP model)
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

5. ITER Shutdown Dose Rate Experiment (FNG)
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

6. ITER Shutdown Dose Rate Experiment (FNG)
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

7. IFMIF Neutronics D(Li,xn) source function
Reaction models & evaluated data files
MCNP  MC codes McDeLi, McDeLicious
Data base development E 20 MeV
INPE Obninsk /FZK co-operation
Transport & activation data files
ENDF-6 data format
Design & optimisation irradiation test modules
High flux test module (HFTM)
Irradiation characteristics
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

8. D-Li neutron source term
6,7Li + d cross-section evaluations (E 50 MeV)
 A. Konobeyev et al, Nucl. Sci. Eng. 139, 1-23 (2001)
Evaluation methodology
Diffraction theory for elastic scattering & deuteron break-up
Modified intranuclear cascade model for stripping reactions
Code DISCA/3D & microscopic experimental data
ENDF-6 evaluated data files
DDX neutron emission cross-sections (MF=6)
Processed with NJOY/ACER for use with MC-codes
Advanced Monte Carlo procedure for source term calculations using d+ 6,7Li data files: “McDeLicous”
 S. Simakov, this meeting
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

9. IFMIF neutron flux spectrum
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

10. Intermediate Energy Activation File
Complete activation data library IEAF-2001
679 nuclides (1<Z<84),  excitation functions
E  150 MeV; E  20 MeV: EAF-99 activation cross-sections
ENDF-6 format, MT=5, LAW=0, MF=2 skeleton
Processed with NJOY/GROUPR; full GENDF data library
Applied to IFMIF HFTM activation analysis with ALARA activation code (P. Wilson, UW)
IEAF-2001 to be distributed via NEA Data Bank
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001

11. Intermediate Energy Data Evaluations
INPE Obninsk/FZK co-operation
1H, 56Fe, 23Na, 39K, 28Si, 12C, 52Cr, 51V (50 MeV); 6,7Li, 9Be (150 MeV)
LANL 150 MeV data evaluations
1,2H, 9Be, 12C, 16O, 14N, 27Al, 28,29,30Si, 31P, 40Ca, 50,52,53,54Cr, 54,56,57,58Fe, 58,60,61,62,64Ni, 63,65Cu, 93Nb, 182,183,184,186 W, 196,198, 199, 200, 201, 202, 204 Hg, 206, 20, 208 Pb, 209Bi
JENDL High Energy File for IFMIF (50 MeV)
12C, 23Na, 24,25,26Mg, 27Al, 28,29,30Si, 39K, 40,42,43,44,46,48Ca, 46,47,48,49,50Ti, V, 50,52,53,54Cr, 55Mn, 54,56,57,58Fe, 58,60,61,62,64Ni, 63,65Cu, 89Y, ,94,95,96,97,98,100Mo,180,182,183,184,186 W
NRG Petten/ CEA Bruyeres-les-Chateles co-operation
54,56Fe, 58,60Ni (150 MeV)
IEA International Workshop on Fusion Neutronics, Baden-Baden 18 October 2001