Evaluation of Neutron Nuclear Data for Sodium-23.

Shibata, Kozo

doi:10.3327/jnst.39.1065

Cited by 52 publications

(91 citation statements)

References 39 publications

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“…In general, previous data exhibit sizable discrepancies, both in terms of resonance strength and energy. Correspondingly, similar differences are also found between the ENDF/B-VII.0 and JEFF-3.1 evaluations (the latter data are identical with those in the JENDL-3.3 [28] library). The n TOF data confirm the results of Guber et al [29] around 90 eV, apart from a small difference in the resonance energy.…”

Section: A Comparison With Previous Measurementssupporting

confidence: 76%

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C

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The 233 U(n,f ) cross section has been measured at the white neutron source n TOF in a wide energy range with a dedicated fission ionization chamber. We report here the results from ∼30 meV to 1 MeV neutron energy. The 233 U(n,f ) cross section has been determined relative to a reference sample of 235 U(n,f ) measured simultaneously with the same detector. The very high instantaneous neutron flux and the intrinsically low background of the n TOF installation result in an accuracy around 3% in the whole energy range, while the energy resolution of the neutron beam allows for an accurate description of the fission cross section by means of R-matrix analysis over a wide energy range. The results are, in general, in good agreement with the most recent high-accuracy measurement of this fission cross section, over the more limited range of the previous measurements, and indicated that even the latest evaluations underestimate the cross section in the epithermal region. The present high-quality data provide the basis for a more precise evaluation of the 233 U fission cross section and for improving the reliability of databases needed for the design of new energy systems based on the Th/U cycle.

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Section: A Comparison With Previous Measurementssupporting

confidence: 76%

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C

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“…The European Fusion File which was last distributed as a separate file as EFF-2.4 [13] has become part of JEFF [14]. ENDF [15] and BROND [16] have always included fusion relevant data; and while the JENDL-FF [17] still exists, the last release is old (1999) and JENDL-3.3 [18] contains fusion data. The exception to the rule that fusion data are to be found in the standard data files is for activation.…”

Section: Fendlmentioning

confidence: 99%

Nuclear data for fusion applications

Forrest

2007

Nd2007

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Abstract. Achieving the economically viable release of energy by the fusion process has proved a major scientific and technological challenge. The nuclear reactions involved in the fusion process are well understood, but the interaction of the neutrons with the materials surrounding the plasma is an area of current research. The neutrons have energies larger than those experienced in fission and this has been a driver to extend the types and amounts of nuclear data. Designs for fusion devices require neutron and photon transport calculations to generate the spectra required to provide the nuclear responses. Such calculations require cross section data for all elements present in the device. ITER is the next step on the road to demonstrating the commercial generation of electricity. The importance of nuclear data for ITER was realized many years ago, which led to the release of FENDL-1 in 1995. This contained both general and special purpose files; an example of the latter is activation. Development of these files focused on completeness -including γ production and covariances; the files generally had an upper energy limit of 20 MeV. The types of data in the fusion relevant libraries are sufficient for all foreseeable fusion devices. However, the transition in fusion research from plasma physics towards technology requires an understanding of the materials damage caused by the intense fluxes of neutrons that will be found in power plants. To gain this knowledge a materials test facility, IFMIF, is required. This is planned to operate in parallel with ITER and will use accelerated beams of deuterons striking a flowing lithium target to generating an intense neutron field. The neutrons will mostly be fusion relevant, but there will be a high-energy tail extending up to ∼55 MeV. These high energy neutrons further extend the amount of nuclear data required and have stimulated much theoretical and experimental work covering the energy range >20 MeV. Examples of recent general purpose evaluations, new activation libraries and benchmarking are described and the challenges for nuclear data for fusion discussed.

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“…The ENDF/B-VII thermal capture cross section is approximately 16.9% of the corresponding fission cross section. Integrating over the fission (solid gray line) and capture (solid black line) distributions in figure 4, and roughly accounting for the different detection efficiencies for capture and fission events, leads to a result of ∼15% for the [11] and JEFF-3.1 [12] libraries. The points are experimental data from Silbert and Berreth [13].…”

Section: U(nγ) Cross Section and Capture-to-fission Ratiomentioning

confidence: 99%

Recent actinide nuclear data efforts with the DANCE 4π BaF₂ array

Agvaanluvsan

Becker

Bond

et al. 2007

Nd2007

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Abstract. Much of the recent work in the DANCE collaboration has focused on nuclides of interest to stockpile stewardship, attribution science and the advanced fuel cycle initiative. As an example, we have recently begun a program to produce high precision measurements of the key production and destruction reactions of important nuclear fuel elements and radiochemical diagnostic isotopes. The neutron capture targets that have been fielded under this program include several isotopes of uranium, plutonium and americium. However, neutron capture measurements on many of the actinides are complicated by the presence of γ-rays arising from low energy neutron-induced fission. To overcome this difficulty we have designed and implemented a dual parallel-plate avalanche counter fission-tagging detector. This design provides a high efficiency for detecting fission fragments and is self-contained to allow loading of pre-assembled target/detector assemblies into the neutron beam line at DANCE. An outline of the recent experimental program will be presented as well as preliminary results from neutron capture measurements on 234,235,236 U. Planned measurements on 238,239 Pu will also be discussed.

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Evaluation of Neutron Nuclear Data for Sodium-23.

Cited by 52 publications

References 39 publications

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C

Nuclear data for fusion applications

Recent actinide nuclear data efforts with the DANCE 4π BaF₂ array

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Evaluation of Neutron Nuclear Data for Sodium-23.

Cited by 52 publications

References 39 publications

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal toCalviani1, Praena2, Abbondanno3 et al. 2009Phys. Rev. C

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal toCalviani1, Praena2, Abbondanno3 et al. 2009Phys. Rev. C

Nuclear data for fusion applications

Recent actinide nuclear data efforts with the DANCE 4π BaF2 array

Contact Info

Product

Resources

About

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C

High-accuracyU233(n,f)cross-section measurement at the white-neutron source n_TOF from near-thermal to
Calviani¹,
Praena²,
Abbondanno³
et al. 2009
Phys. Rev. C

Recent actinide nuclear data efforts with the DANCE 4π BaF₂ array