Nuclear data needs for advanced reactor systems: a NEA Nuclear Science Committee initiative

Salvatores, M.; Aliberti, G.; Palmiotti, G.; Rochman, D.; Obložinský, P.; Hermann, M. R.; Talou, P.; Kawano, Toshihiko; Leal, L.C.; Koning, A. J.; Kodeli, I.

doi:10.1051/ndata:07298

Cited by 25 publications

(18 citation statements)

References 9 publications

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“…Among the present WPEC subgroups can be mentioned the high priority nuclear data request list [10], and the nuclear data needs for advanced reactor systems [11].…”

Section: Challenges and Future Developmentsmentioning

confidence: 99%

The art of collecting experimental data internationally: EXFOR, CINDA and the NRDC network

Henriksson

Schwerer

Rochman

et al. 2007

Nd2007

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Abstract. The world-wide network of nuclear reaction data centres (NRDC) has, for about 40 years, provided data services to the scientific community. This network covers all types of nuclear reaction data, including neutroninduced, charged-particle-induced, and photonuclear data, used in a wide range of applications, such as fission reactors, accelerator driven systems, fusion facilities, nuclear medicine, materials analysis, environmental monitoring, and basic research. The now 13 nuclear data centres included in the NRDC are dividing the efforts of compilation and distribution for particular types of reactions and/or geographic regions all over the world. A central activity of the network is the collection and compilation of experimental nuclear reaction data and the related bibliographic information in the EXFOR and CINDA databases. Many of the individual data centres also distribute other types of nuclear data information, including evaluated data libraries, nuclear structure and decay data, and nuclear data reports. The network today ensures the world-wide transfer of information and coordinated evolution of an important source of nuclear data for current and future nuclear applications.

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“…Among the present WPEC subgroups can be mentioned the high priority nuclear data request list [10], and the nuclear data needs for advanced reactor systems [11].…”

Section: Challenges and Future Developmentsmentioning

confidence: 99%

The art of collecting experimental data internationally: EXFOR, CINDA and the NRDC network

Henriksson

Schwerer

Rochman

et al. 2007

Nd2007

Self Cite

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“…The representativity study has been performed with respect to the same reactors recently investigated within the OECD Subgroup 26 for an extensive uncertainty/target accuracy assessment in order to define priority needs in nuclear data improvements [5]: an Advanced Burner Test Reactor (ABTR), a Sodium-cooled Fast Reactor (SFR), a large sodium-cooled fast reactor, referred as EFR, a Gas-cooled Fast Reactor (GFR), a Lead-cooled Fast Reactor (LFR), an Accelerator-Driven System (ADS), and an extended burnup (100 GWd/t) Pressurized …”

Section: Systems Under Studymentioning

confidence: 99%

OSMOSE experiment representativity studies.

Aliberti¹,

Klann²

2007

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The OSMOSE experimental program, carried out at the MINERVE facility by the CEA-Cadarache (France), aims at producing very accurate reactivity-sample worth measurements for a series of actinides in various spectra, from very thermalized to very fast. In order to qualify the relevant experimental configurations for the achievement of the proposed goals, calculations have been performed to investigate the similarity of the flux spectra at the sample position of different OSMOSE configurations with the neutron energy distributions characterizing existing thermal and fast reactors proposed under the advanced reactor programs Gen-IV, GNEP and NGNP.

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“…The need for nuclear data covariances (uncertainties and correlations) is becoming increasingly more important for a number of applications, including the development of next generation nuclear power reactors known as "Gen-IV", advanced fuel cycles, transmutation and shielding design [1,2]. Recent progress in transport computer codes and improved evaluated nuclear data allow to replace expensive and time consuming measurements on mock-up assemblies with much faster and cheaper numerical simulations.…”

Section: Introductionmentioning

confidence: 99%

Neutron cross section covariances from thermal energy to 20 MeV

Rochman¹,

Herman²,

Obložinský³

et al. 2007

Nd2007

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Abstract. We describe new method for energy-energy covariance calculation from the thermal energy up to 20 MeV. It is based on three powerful basic components: (i) Atlas of Neutron Resonances in the resonance region; (ii) the nuclear reaction model code EMPIRE in the unresolved resonance and fast neutron regions, and (iii) the Bayesian code KALMAN for correlations and error propagation. Examples for cross section uncertainties and correlations on 90 Zr and 193 Ir illustrate this approach in the resonance and fast neutron regions.

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Nuclear data needs for advanced reactor systems: a NEA Nuclear Science Committee initiative

Cited by 25 publications

References 9 publications

The art of collecting experimental data internationally: EXFOR, CINDA and the NRDC network

The art of collecting experimental data internationally: EXFOR, CINDA and the NRDC network

OSMOSE experiment representativity studies.

Neutron cross section covariances from thermal energy to 20 MeV

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