R-matrix analysis of the {sup 240}Pu neutron cross sections in the thermal to 5700 eV energy range

Technical Report · Fri Aug 01 04:00:00 EDT 1997

DOI:https://doi.org/10.2172/631268· OSTI ID:631268

Derrien, H ^[1]; Bouland, O ^[2]; Larson, N M; Leal, L C ^[3]

---

1. OECD, Paris (France). Nuclear Energy Agency Data Bank
2. Commissariat Energie Atomique, Saint Paul-lez-Durance (France). Centre d`Etudes
3. Oak Ridge National Lab., TN (United States)

Resonance analysis of high resolution neutron transmission data and of fission cross sections were performed in the neutron energy range from the thermal regions to 5,700 eV by using the Reich-Moore Bayesian code SAMMY. The experimental data base is described and the method of analysis is given. The experimental data were carefully examined in order to identify more resonances than those found in the current evaluated data files. The statistical properties of the resonance parameters are given. A new set of the average values of the parameters is proposed, which could be used for calculation of the average cross sections in the unresolved resonance region. The resonance parameters are available IN ENDF-6 format at the national or international data centers.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE Office of Energy Research, Washington, DC (United States)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 631268
• Report Number(s): ORNL/TM--13450; ON: DE98005996
• Country of Publication: United States
• Language: English

Related Subjects

66 PHYSICS
99 GENERAL AND MISCELLANEOUS
CROSS SECTIONS
DATA ANALYSIS
EV RANGE
FISSION
KEV RANGE 01-10
NEUTRON REACTIONS
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
PLUTONIUM 240
R MATRIX
RESONANCE