Fission-product energy release for times following thermal-neutron fission of /sup 235/U between 2 and 14000 seconds

Dickens, J.K.; Emery, J.F.; Love, T.A.; McConnell, J.W.; Northcutt, K.J.; Peelle, R.W.; Weaver, H.

doi:10.2172/5348997

Cited by 21 publications

(18 citation statements)

References 3 publications

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“…7) It was found that the summation calculation based on it overestimated the -ray component, and largely underestimated the -ray component of the decay heat after a fission burst measured at Yayoi 14) and Oak Ridge. 15,16) The same kind of disagreement 17) was experienced also in the US (preliminary version of ENDF/B-V) 18) and in Europe. Yoshida and Nakasima 7) pointed out that the calculations based on the preliminary version of the JNDC FP Decay Data File were suffering from the pandemonium problem through the use of published decay schemes to derive the values of E and E for individual short-lived (or highly Q -valued) FP nuclides.…”

Section: Pandemonium Problem and Theoretical Correctionsmentioning

confidence: 82%

Reconsideration of the Theoretical Supplementation of Decay Data in Fission Product Decay Heat Summation Calculations

Hagura

Yoshida

Tachibana

2006

Journal of Nuclear Science and Technology

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In the early stage of the development of the fission product (FP) decay data library for decay-heat summation calculations a serious disagreement between calculations and sample-irradiation measurements was experienced world wide. This problem was essentially circumvented by introduction of the nuclear model calculations. By applying the recent results using the total absorption gamma-ray spectrometer to the decay heat calculations we found that TAGS results seem to be free from the pandemonium problem and, in this respect, it provides a solid basis of the summation calculations without the supplementation of the nuclear model calculations. Among the typical FP nuclides which deserve the future TAGS experiment there are 98 Nb, 100 Nb, 105 Mo and 102 Tc and others from the present survey.

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Section: Pandemonium Problem and Theoretical Correctionsmentioning

confidence: 82%

Reconsideration of the Theoretical Supplementation of Decay Data in Fission Product Decay Heat Summation Calculations

Hagura

Yoshida

Tachibana

2006

Journal of Nuclear Science and Technology

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“…The decay heats from 235 U thermal fission have been calculated with the ORIGEN-S code and compared with the measurements of ORNL [9]. Figure 2 shows comparisons of the decay heats with measurements and calculated results with different fission yields data.…”

Section: Resultsmentioning

confidence: 99%

Fission yields data generation and benchmarks of decay heat estimation of a nuclear fuel

et al. 2017

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Abstract. Fission yields data with the ENDF-6 format of 235 U, 239 Pu, and several actinides dependent on incident neutron energies have been generated using the GEF code. In addition, fission yields data libraries of ORIGEN-S, -ARP modules in the SCALE code, have been generated with the new data. The decay heats by ORIGEN-S using the new fission yields data have been calculated and compared with the measured data for validation in this study. The fission yields data ORIGEN-S libraries based on ENDF/B-VII.1, JEFF-3.1.1, and JENDL/FPY-2011 have also been generated, and decay heats were calculated using the ORIGEN-S libraries for analyses and comparisons.

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“…The measured data are taken from those performed at Oak Ridge National Laboratory for 235 U and 239 Pu thermal neutron fission [1,2] and those at YAYOI of Tokyo University for 238 U fast neutron fission [6]. The nuclides of 235 U, 239 Pu, and 238 U are important fissioning nuclides in the decay heat analysis in a light water reactor.…”

Section: Comparison Of Decay Heat Calculation Using Jendl Jeff and mentioning

confidence: 99%

“…As there are many short-lived nuclides for which experimental difficulties are encountered, the accurate nuclear data are, in actuality, unavailable for such nuclides. Under such circumstance, integral measurements have been undertaken in order to acquire reliable values of the decay heat power covering short cooling times after fission [1][2][3][4][5][6][7][8][9]. These integral-measured decay heat power data are employed to assess the summation calculation using microscopic data, that is, the decay and fission yield data of fission products.…”

Section: Introductionmentioning

confidence: 99%

Uncertainty analyses of decay heat summation calculations using JENDL, JEFF, and ENDF files

Katakura

2013

Journal of Nuclear Science and Technology

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The uncertainty analyses of decay heat calculation were carried out using major evaluated nuclear data files, JENDL, JEFF, and ENDF. The uncertainties were obtained from the sensitivity of individual fission product nuclide to the decay heat summation calculation. The summation calculation was performed for a burst fission. The sensitivities derived from the analyses were for decay energy, fission yield, and decay constant among the nuclear data included in the summation calculation. The uncertainties of the calculations at 0.1 s after a fission burst are ∼10% for JENDL and ∼8% for JEFF and ENDF and those at 10 4 s are less than 2% for all cases. The main differences came from the different adoption of the energy uncertainty. The sensitivity analysis can be used to improve the decay data for decay heat calculation.

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Fission-product energy release for times following thermal-neutron fission of /sup 235/U between 2 and 14000 seconds

Abstract: 12. II. Copy Reproduction and Distribution

Cited by 21 publications

References 3 publications

Reconsideration of the Theoretical Supplementation of Decay Data in Fission Product Decay Heat Summation Calculations

Reconsideration of the Theoretical Supplementation of Decay Data in Fission Product Decay Heat Summation Calculations

Fission yields data generation and benchmarks of decay heat estimation of a nuclear fuel

Uncertainty analyses of decay heat summation calculations using JENDL, JEFF, and ENDF files

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