ENDF/B-IV fission-product files: summary of major nuclide data

England, T.R.; Schenter, R.E.

doi:10.2172/4136569

Cited by 15 publications

(14 citation statements)

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“…We have used nuclear data from ENSDF, ENDF/B.VII.l and nuclear data libraries included in ORIGEN-S from Scale program (decay data, branching ratios, etc.) [16,17,18,19]. The calculated antineutrino energy spectra of 235 U, 238 U, 239 Pu and 241 Pu folded with cross-section for inverse beta decay are presented on Fig.…”

Section: B Fuel Composition Monitoring 1) Calculation Of Reactor Antmentioning

confidence: 99%

Detector of reactor antineutrinos with plastic stintillation bars

Georgadze¹,

Pavlovych²

2015

Nucl. Phys. At. Energy

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Abstract⎯ Conceiving the possibility of using plastic scintillator bars as robust detectors for antineutrino detection for the remote reactor monitoring and nuclear safeguard application we study expected basic performance by Monte Carlo simulation. We present preliminary results for a 1 m 3 highly segmented detector made of 100 rectangular scintillation bars forming an array which is sandwiched at both sides by the continuous light guides enabling light sharing between all photo detectors. Light detection efficiency is calculated for several light collection configurations, considering different scintillation block geometries and number of photo-detectors. The photo-detectors signals are forming the specific hit pattern, which is characterizing the impinging particle. The statistical analysis of hit patterns allows effectively select antineutrino events and rejects backgrounds. To evaluate detector sensitivity to fuel isotopic composition evolution during fuel burning cycle we have calculated antineutrino spectra. The statistical analyses of the antineutrino spectra for several dates of fuel burning cycle, folded with 15% FWHM at 1 MeV energy resolution of the detector, prove the possibility of proposed detector to measure fuel composition evolution during fuel cycle.

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Section: B Fuel Composition Monitoring 1) Calculation Of Reactor Antmentioning

confidence: 99%

Detector of reactor antineutrinos with plastic stintillation bars

Georgadze¹,

Pavlovych²

2015

Nucl. Phys. At. Energy

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“…1, was constructed in the following manner, 3.0 x 10 6 eV -1.0 x 10 7 eV <J)(E) assumes the shape of a fission spectrum with the temperature of 1.3427 MeV, approximating the calculated MC^ multigroup spectrum. 1.0 x 10 7 eV -1.257 x 10 7 eV <J>(E) varies as l/E. 1.257 x 10 7 eV -1.557 x 10 7 eV $(E) is a velocity exponential fusion peak.…”

Section: A Prs Flux Weighting Functionmentioning

confidence: 99%

“…1.0 x 10 7 eV -1.257 x 10 7 eV <J>(E) varies as l/E. 1.257 x 10 7 eV -1.557 x 10 7 eV $(E) is a velocity exponential fusion peak. 1.557 x 10 7 eV -2.0 x 10 7 eV 4>(E) varies as l/E.…”

Section: A Prs Flux Weighting Functionmentioning

confidence: 99%

“…1.257 x 10 7 eV -1.557 x 10 7 eV $(E) is a velocity exponential fusion peak. 1.557 x 10 7 eV -2.0 x 10 7 eV 4>(E) varies as l/E. In the energy range of typical LWR calculations below 10 MeV, the weighting function accurately describes the appropriate spectrum.…”

Section: A Prs Flux Weighting Functionmentioning

confidence: 99%

“…Basic nuclear data parameters for all nuclides contained in the library have been succinctly presented in Ref. 1, listing half-lives, modes of decay, decay branching fractions, and average decay energies.…”

Section: Introductionmentioning

confidence: 99%

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Multigroup and few-group cross sections for ENDF/B-IV fission products; the TOAFEW collapsing code and data file of 154-group fission-product cross sections. [In FORTRAN]

Wilson¹,

England²,

LaBauve³

1978

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The ENDF/B-IV fission-product data file includes data describing 824 nuclides. Cross sections, given for 181 of these nuclides, have been processed into 154 neutron energy groups. The production of the data file is described. The TOAFEW code, useful in collapsing the multigroup values to few-group cross sections, is presented with instructions and examples of its use. The file of multigroup cross sections is available on request. I. c^ in o in o in c* tn o in in in ^n in u^ in in fy ^ĵ CM cvj r j njt oooaoo oooc J UJ U} UJ UJ UJUJUJUJUJUJUJUJUJUJUJUJUJUJUJUJUJUlUJUJUJUJlxlUJUJUJUJUJUlUJUl J ^D C* ^^ *3 ^D O O C^ ^? C) ^^ ^D O ^5 O O-^3 C3 C3 CJ i3 3 3 ^} >3 ^3 C^7 O oooo oooooooooooooooooooooo-^oooooooo JOOOO OOOOOOOOOOOOOOOOOOOOOOCIOOOOOOOO JOOOO oooooooooooooooooooooocooooooom C\l f\l C\i roro ro m no m rnci zs ^ ^ ^ \f\ m in in tA I I 1 I • I lOOC'O'aoOiO'a'O crftn tntnininin-=rir»-^'-=S"-S'3 >-3'='"^'^T^'.=r-5i3 i ir^3'^"* w^f| nro OOOOOOOOOOOOOOOOOOOOOOOOOOOOOCiOOOOOOOO

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Nuclear Physics Data for Reactor Kinetics

Walker

Weaver

1979

Advances in Nuclear Science and Technology

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ENDF/B-IV fission-product files: summary of major nuclide data

Cited by 15 publications

References 0 publications

Detector of reactor antineutrinos with plastic stintillation bars

Detector of reactor antineutrinos with plastic stintillation bars

Multigroup and few-group cross sections for ENDF/B-IV fission products; the TOAFEW collapsing code and data file of 154-group fission-product cross sections. [In FORTRAN]

Nuclear Physics Data for Reactor Kinetics

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