Fission Temperatures as a Function of the Average Number of Neutrons from Fission

Howerton, R.J.; Doyas, R.J.

doi:10.13182/nse71-a22378

Cited by 13 publications

(2 citation statements)

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“…The fission neutron spectra were estimated from the systematics derived by Howerton and Doyas. 78) The number of prompt neutrons per fission was determined from Howerton's systematics, 79) and the delayed neutrons from Tuttle's systematics. 80) This method was adapted to Cm isotopes, 235 Np, 237 Pu, 244 Pu, 246 Pu, 247 Bk and 249 Cf.…”

Section: Minor Actinide Datamentioning

confidence: 99%

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.

Shibata

Kawano

Nakagawa

et al. 2002

J. Nucl. Sci. Technol.

463

306

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Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 235 U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

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Section: Minor Actinide Datamentioning

confidence: 99%

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.

Shibata

Kawano

Nakagawa

et al. 2002

J. Nucl. Sci. Technol.

463

306

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“…The spectra of prompt fission neutrons from the reaction 238 U(n, F ) have been vigorously studied both experimentally and theoretically since the discovery of nuclear fission [1,2]. In the energy range of emissive fission [ 238 U(n, F ) = 238 U(n, f ) + 238 U(n, f ) + 238 U(n, 2nf ) + .…”

Section: Introductionmentioning

confidence: 99%

10.1007/s11450-008-1002-2

2010

CrossRef Listing of Deleted DOIs

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The spectra of prompt fission neutrons from the reaction 238 U(n, F ) for neutrons of energy in the range E n ≤ 20 MeV are interpreted within the statistical model. It is shown that exclusive spectra of prefission neutrons emitted in (n, xnf ) reactions play a decisive role in describing the observed promptfission-neutron spectra and determine the average energies of prompt-fission neutrons. The dependence of the effect of prefission neutrons on the fissility of a target nucleus is demonstrated for the reactions

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Microscopic Spectra Evaluation. Semiempirical Modeling

Корнилов

2014

Fission Neutrons

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Fission Temperatures as a Function of the Average Number of Neutrons from Fission

Cited by 13 publications

References 0 publications

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3.

10.1007/s11450-008-1002-2

Microscopic Spectra Evaluation. Semiempirical Modeling

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