JRC-IRMM/ORNL Collaboration on Nuclear Data for Nuclear Criticality Safety - 14486

Conference · Tue Sep 15 04:00:00 EDT 2015

OSTI ID:23100908

Heyse, J.; Kopecky, S.; Lampoudis, C.; Paradela, C.; Plompen, A.; Schillebeeckx, P.; Siegler, P. ^[1]; Guber, K.; Leal, L. ^[2]

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1. EC-JRC-IRMM, SN3S Unit Retieseweg 111, 2440 Geel (Belgium)
2. Oak Ridge National Laboratory P.O. Box 2008, Oak Ridge, TN 37831 (United States)

Concerns about using cross sections recommended in the main evaluated data libraries (i.e. ENDF/B, JEFF and JENDL) for nuclear criticality calculations have been a prime motivator for new cross section measurements. The measurements and evaluations discussed in this work are part of a collaboration between the Oak Ridge National Laboratory (ORNL) and the Institute for Reference Material and Measurements of the Joint Research Center (JRC-IRMM) of the European Commission (EC). They are performed in response to the US Nuclear Criticality Safety Program (NCSP) data needs. In particular, the NCSP five-year plan encompasses a listing of elements that have been identified for measurements and evaluations to address issues on criticality safety applications. This listing is based on data deficiency concerns in practical applications that are conveyed by criticality safety practitioners. In general these deficiencies are obtained through the analysis of benchmark calculations. A wealth of evaluations in the main libraries were derived from results of measurements made with poor time-of-flight resolution, and also the description of some data in the neutron energy range above several tens of keV is crude. This impacts both the resolved and unresolved resonance region, and leads to bias effects when resonance structures play an important role. As a consequence only average corrections can be applied in calculations for nuclear criticality calculations where self-shielding, multiple scattering, or Doppler broadening are important. This can lead to erroneous results. Furthermore, many evaluations for nuclides having small neutron-capture cross sections show erroneously high cross sections because the influence of the neutron sensitivity of the old measurement systems was underestimated. Although their neutron capture cross sections are small, these nuclides, if occurring in large amounts, can be important absorbers in criticality calculations, so an accurate determination of these cross sections is required. Over the last seven years the JRC-IRMM/ORNL collaboration has produced many neutron induced cross section data using the Geel Electron Linear Accelerator (GELINA) neutron time-of-flight facility. This facility is ideally suited to measure total, fission and capture cross sections in the energy range from 1 eV to ∼600 keV, which is important for nuclear criticality calculations. In this paper the facility and experimental set-ups at GELINA will be described together with the data reduction and analysis procedures which result in experimental observables including their full covariance information. The importance of combining transmission and partial cross section data will be emphasized. We will give a list of the measured nuclides and discuss the impact of the resulting data and evaluations. (authors)

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 23100908
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BENCHMARKS
CRITICALITY
DOPPLER BROADENING
FISSION
KEV RANGE
LINEAR ACCELERATORS
MULTIPLE SCATTERING
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
SAFETY
SELF-SHIELDING
TOTAL CROSS SECTIONS