B. Morillon, L. Leal?, G. Noguere y, P. Romain, H. Duarte. April U, 238 U and 239 Pu JEFF-3.3T1 evaluations
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1 B. Morillon, L. Leal?, G. Noguere y, P. Romain, H. Duarte CEA,DAM,DIF F-9297 Arpajon, France y CEA,DEN Cadarache, France? IRSN Fontenay-aux-Roses, France April 206
2 239 Pu : what's new New FILES 2, Completely new evaluations Calculations done with the TALYS code, New softer prompt ssion neutron spectra, with new prompt neutron multiplicity, New OMP parameters : New elastic and inelastic cross sections,! New (n,) cross sections,..., Fission cross sections from Standards, but close to the BRC model calculation, Covariances (FILE 33).. TALYS.6 developped by A.J. Koning et al.
3 239 Pu : what's new 235 U Fission spectra, Multiplicity, OMP parameters, Fission standards, FILES 2, Covariances (T6 ). 238 U Fission spectra, Multiplicity, OMP parameters, Fission standards, Covariances (COMAC 2 ). 239 Pu Fission spectra, Multiplicity, OMP parameters, Fission standards, FILES 2, Covariances (COMAC 2 ).. TASMAN code developped by A.J. Koning and D. Rochman 2. COMAC, covariance library from CEA/Cadarache
4 239 Pu, 235 U : new OMP parameters! new C:N: 5 Cross Section (barn) Pu σ CN =σ R -σ DI JEFF33T JEFF Neutron Energy (MeV)
5 239 Pu, 235 U : new OMP parameters! new C:N: 5 Cross Section (barn) U σ CN =σ R -σ DI JEFF33T JEFF Neutron Energy (MeV)
6 239 Pu, 235;238 U : evaluated and standard ssion cross sections Fission Cross Section (barn) n Pu IAEA Standard BRC205/TALYS Neutron Energy (MeV)
7 239 Pu, 235;238 U : evaluated and standard ssion cross sections Fission Cross Section (barn) n U IAEA Standard BRC205/TALYS Neutron Energy (MeV)
8 239 Pu, 235;238 U : evaluated and standard ssion cross sections Fission Cross Section (barn) n U IAEA Standard BRC205/TALYS 0-0 Neutron Energy (MeV)
9 239 Pu and 235 U : average ssion energy 239 Pu Average Fission Energy (MeV) n Pu JEFF-3.3T (0.4-7 MeV) JEFF-3.3T Chatillon et al. (204) (0.4-7 MeV) 2. E th =2.096 MeV 2.05 Neutron Energy (MeV) 0
10 239 Pu and 235 U : average ssion energy 239 Pu 235 U Average Fission Energy (MeV) n Pu JEFF-3.3T (0.4-7 MeV) JEFF-3.3T Chatillon et al. (204) (0.4-7 MeV) Average Fission Energy (MeV) n U JEFF-3.3T Ethvignot et al. (2005) 2. E th =2.096 MeV Neutron Energy (MeV) 0.9 E th =2.000 MeV 0 Neutron Energy (MeV)
11 JEFF ;238 U JEFF-3.3T.008 HEU MET FAST JEFF3.2 JEFF3.2 + U 235,238 JEFF-3.3T dep. U ref. Cylinder whitout ref. K eff Godiva water ref. whitout ref. 0a 0b 04a 04b 04c a 8b a 32b 32c 32d polyethylene ref. steel ref. whitout ref. Flattop U ref. U ref.
12 JEFF ;238 U JEFF-3.3T IEU MET FAST JEFF3.2 JEFF3.2 + U 235,238 JEFF-3.3T K eff.002 Big Ten Jemima a 0b 0c 0d 07a 07b
13 JEFF ;238 U JEFF-3.3T HEU SOL THERM.0 JEFF3.2 JEFF3.2 + U 235,238 JEFF-3.3T.005 K eff heavy water ref. water ref. 04a 04b 04c 04d 04e 04f 09a 09b 09c 09d
14 JEFF ;238 U JEFF-3.3T.008 HEU-MET-INTER JEFF3.2 JEFF3.2 + U 235,238 JEFF-3.3T K eff HMI006 : ZEUS EXPERIMENTS 2 3 4
15 ENDF/B-VII ;238 U JEFF-3.3T.008 HEU MET FAST ENDF/B-VII. ENDF/B-VII. + U 235,238 JEFF-3.3T dep. U ref. Cylinder whitout ref. K eff Godiva water ref. whitout ref. 0a 0b 04a 04b 04c a 8b a 32b 32c 32d polyethylene ref. steel ref. whitout ref. Flattop U ref. U ref.
16 ENDF/B-VII ;238 U JEFF-3.3T IEU MET FAST ENDF/B-VII. ENDF/B-VII. + U 235,238 JEFF-3.3T K eff.002 Big Ten Jemima a 0b 0c 0d 07a 07b
17 ENDF/B-VII ;238 U JEFF-3.3T HEU SOL THERM.0 ENDF/B-VII. ENDF/B-VII. + U 235,238 JEFF-3.3T.005 K eff heavy water ref. water ref. 04a 04b 04c 04d 04e 04f 09a 09b 09c 09d
18 ENDF/B-VII ;238 U JEFF-3.3T.008 HEU-MET-INTER ENDF/B-VII. ENDF/B-VII. + U 235,238 JEFF-3.3T K eff HMI006 : ZEUS EXPERIMENTS 2 3 4
19 JEFF Pu JEFF-3.3T.0 PU MET FAST JEFF3.2 JEFF3.2 + Pu JEFF-3.3T duralium ref K eff Jezebel 239 Pu Jezebel 240 Pu Flattop U ref. 239 Pu U ref. Pu cylinders surrounded by water beryllium ref. dep. U ref b 6c 6d 6e 6f a 22b 23a 23b 24a 24b 28a 28b 29a 29b 37a 37b 37c 37d 37e 37f 37g Pu sphere graphyte ref. polyethylene ref. steel ref. 239 Pu sphere Pu cylinders surrounded by water dep. U ref.
20 JEFF Pu JEFF-3.3T.02 PU SOL THERM.05 JEFF3.2 JEFF3.2 + Pu JEFF-3.3T K eff water reflector without reflector 0b 0c 0d 0e 0f 04a 04b 04c 04d 04e 04f 04g 04h 6a 6b 6c 6d 6e 8a 8b 8c 8d 8e 8f 8g
21 ENDF/B-VII Pu JEFF-3.3T.0 PU MET FAST ENDF/B-VII. ENDF/B-VII. + Pu JEFF-3.3T duralium ref K eff Jezebel 239 Pu Jezebel 240 Pu Flattop U ref. 239 Pu U ref. Pu cylinders surrounded by water beryllium ref. dep. U ref b 6c 6d 6e 6f a 22b 23a 23b 24a 24b 28a 28b 29a 29b 37a 37b 37c 37d 37e 37f 37g Pu sphere graphyte ref. polyethylene ref. steel ref. 239 Pu sphere Pu cylinders surrounded by water dep. U ref.
22 ENDF/B-VII Pu JEFF-3.3T.02 PU SOL THERM.05 ENDF/B-VII. ENDF/B-VII. + Pu JEFF-3.3T K eff water reflector without reflector 0b 0c 0d 0e 0f 04a 04b 04c 04d 04e 04f 04g 04h 6a 6b 6c 6d 6e 8a 8b 8c 8d 8e 8f 8g
23 238 and 239 Pu JEFF-3.3T evaluation New FILE 2, Completely new evaluations New softer prompt ssion neutron spectra, with new prompt neutron multiplicity, New OMP parameters, New elastic and inelastic cross sections, Fission cross section from IAEA standards, but close to the BRC model calculations. Covariances (COMAC or T6).
24 238 and 239 Pu JEFF-3.3T evaluation New FILE 2, Completely new evaluations New softer prompt ssion neutron spectra, with new prompt neutron multiplicity, New OMP parameters, New elastic and inelastic cross sections, Fission cross section from IAEA standards, but close to the BRC model calculations. Covariances (COMAC or T6). Benchmarks 239 Pu benchmarks and 235;238 U benchmarks : results obtained with JEFF-3.3T are at least as good as with JEFF-3.2.
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