Cross sections for (<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" display="inline"><mml:mi>n</mml:mi><mml:mo>,</mml:mo><mml:mn>2</mml:mn><mml:mi>n</mml:mi></mml:math>) and (<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" display="inline"><mml:mi>n</mml:mi><mml:mo>,</mml:mo><mml:mn>3</mml:mn><mml:mi>n</mml:mi></mml:math>) reactions above 14 MeV

Veeser, L. R.; Arthur, E.D.; Young, P.G.

doi:10.1103/physrevc.16.1792

Cited by 94 publications

(40 citation statements)

References 21 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Figure 3 presents a comparison of the 103 Rh(n,2n) evaluations with experimental data. Our evaluation reproduces the newer experimental data [8,9] well, which are higher than the older ones [10,11]. We note that ENDF/B-VI.8 is lower than other libraries and experimental data, and it shows unphysical behavior at high energies, due to the emission of the (n,3n) reaction channel.…”

Section: Resultssupporting

confidence: 74%

“…Neutron cross sections for 32 fission products were evaluated from 10 −5 eV to 20 MeV under the KAERI-BNL collaboration 141 Pr, and 24 isotopes in complete isotopic chains for Nd (8), Sm (9) and Dy (7). The evaluated data were converted into ENDF-6 formatted files, verified with a set of checking codes, processed with the code NJOY-99.161, and subjected to test runs with the code MCNP5 to ensure that the files can be used in transport calculations.…”

Section: Discussionmentioning

confidence: 99%

See 1 more Smart Citation

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Kim

Lee

Herman

et al. 2007

Nd2007

View full text Add to dashboard Cite

Abstract. Neutron cross sections for fission products play an important role not only in the design of extended burnup core and fast reactors, but also in the study of the backend fuel cycle and the criticality analysis of spent fuel. New evaluations for the ENDF/B-VII.0 library were performed by the KAERI-BNL collaboration for the following 32 fission products: 95 Nd, 144,147,[148][149][150][151][152][153][154] and 156,158,[160][161][162][163][164] Dy. The evaluations cover a large amount of reaction channels, from 10 −5 eV to 20 MeV, including thermal, resolved, unresolved resonance regions, and fast neutron region.

show abstract

Section: Resultssupporting

confidence: 74%

Section: Discussionmentioning

confidence: 99%

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Kim

Lee

Herman

et al. 2007

Nd2007

View full text Add to dashboard Cite

show abstract

“…No neutron induced reaction cross section for reaction 89 Y(n,4n) were found in the EXFOR data base or open literature. Only the data for the cross section of 89 Y(n, 2n) and several points of 89 Y(n, 3n) 87 Y reactions we could find [12], [13]. TALYS is a software for the simulation of nuclear reactions.…”

Section: Assignation Of the Microscope Cross Section For The (Nxn) Rmentioning

confidence: 99%

“…Comparisons of average neutron flux densities and average neutron flux densities per deuteron and their energy for the three neutron energy ranges (11,(5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(15)(16)(17)(18)(19)(20)8 MeV, 20,7 MeV, 32,7-100 MeV) and for the deuteron beam energy equal to 4 GeV of both experiments (in March and December 2011 ) were performed.…”

mentioning

confidence: 99%

Lead shielding impact on fast neutron spectrum (>10MeV) in QUINTA uranium target

Szuta¹,

Strugalska-Gola²,

Kilim³

et al. 2015

Proceedings of XXII International Baldin Seminar on High Energy Physics Problems — PoS(Baldin ISHEPP XXII)

View full text Add to dashboard Cite

The QUINTA uranium target is a deeply sub-critical active core consisting of 512 kg of natural uranium rods arranged hexagonally. The target is irradiated by a pulsed beam of relativistic ions using the JINR NUCLOTRON accelerator. In the paper the lead shielding impact on fast neutron spectrum in the QUINTA uranium target is studied. The fast neutron energy spectra inside the volume of the QUINTA uranium target using threshold reaction in natural yttrium ( 89 Y) were measured for the same deuteron energy of 4 GeV when the uranium target of the assembly was enfolded with the lead shielding and without the shielding. The (n,xn) reaction rates of yttrium samples located inside the assembly were determined through gamma spectrometry. The measurement show that the neutron flux density increases in whole volume of the QUINTA assembly due to the lead shielding. The lead shielding influence on the neutron spectra is more pronounced in the volume located closer to the shielding. Here you can write the abstract for your paper.

show abstract

“…For example, it is known that the content of Yttrium can improve the corrosion resistance of Zirconium-base alloy, but the data on 89 Y (n, 2n) cross sections were mostly reported up to the neutron energy of 30 MeV [2,3], and only a few data exist above 30 MeV [4]. Also, the data on 89 Y (n, 3n) reactions at neutron energies above 30 MeV are only scarcely measured with large uncertainties [5].…”

Section: Introductionmentioning

confidence: 99%

Measurements of ⁸⁹Y(n,2n)⁸⁸Y and ⁸⁹Y(n,3n)⁸⁷Y, ^87mY cross sections for fast neutrons at KIRAMS

Bak

Ham

et al. 2017

EPJ Web Conf.

View full text Add to dashboard Cite

Abstract.A proton cyclotron MC-50 in Korea Institute of Radiological & Medical Science (KIRAMS) is used to carry out neutron activation experiments with Y 2 O 3 targets irradiated with neutron beams of a continuous spectrum produced by proton beams on a thick beryllium target. Neutrons are generated by 9 Be (p, n) reaction with an incident proton intensity of 20 µA. The neutron spectra generated by proton beams of 30, 35, and 40 MeV are calculated by GEANT4 simulations. Nb powders are used for neutron flux monitoring by measuring the activities of 92m Nb through the reaction 93 Nb (n, 2n). By using a subtraction method, the average cross section of 89 Y(n,2n) and 89 Y(n,3n) reactions at the neutron energies of 29.8 ± 1.8 MeV and 34.8 ± 1.8 MeV are extracted and are found to be close to the existing cross sections from the EXFOR data and the evaluated nuclear data libraries such as TENDL-2015 or EAF-2010.

show abstract

Cross sections for (n,2n) and (n,3n) reactions above 14 MeV

Cited by 94 publications

References 21 publications

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Lead shielding impact on fast neutron spectrum (>10MeV) in QUINTA uranium target

Measurements of ⁸⁹Y(n,2n)⁸⁸Y and ⁸⁹Y(n,3n)⁸⁷Y, ^87mY cross sections for fast neutrons at KIRAMS

Contact Info

Product

Resources

About

Cross sections for (n,2n) and (n,3n) reactions above 14 MeV

Cited by 94 publications

References 21 publications

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

New ENDF/B-VII.0 evaluations of neutron cross sections for 32 fission products

Lead shielding impact on fast neutron spectrum (>10MeV) in QUINTA uranium target

Measurements of 89Y(n,2n)88Y and 89Y(n,3n)87Y, 87mY cross sections for fast neutrons at KIRAMS

Contact Info

Product

Resources

About

Measurements of ⁸⁹Y(n,2n)⁸⁸Y and ⁸⁹Y(n,3n)⁸⁷Y, ^87mY cross sections for fast neutrons at KIRAMS