Delayed beta- and gamma-ray production due to thermal-neutron fission of /sup 235/U, spectral distributions for times after fission between 2 and 14,000 sec: tabular and graphical data

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

doi:10.2172/6618867

Cited by 5 publications

(3 citation statements)

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“…The mean and standard deviation of the decay heat is then computed over the 500 calculations. The uncertainties are generally lower than the experimental data (Tobias [9] ,Dickens [10]). …”

Section: Decay Heat Benchmarksmentioning

confidence: 86%

Fission yield covariances for JEFF: A Bayesian Monte Carlo method

et al. 2017

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Abstract. The JEFF library does not contain fission yield covariances, but simply best estimates and uncertainties. This situation is not unique as all libraries are facing this deficiency, firstly due to the lack of a defined format. An alternative approach is to provide a set of random fission yields, themselves reflecting covariance information. In this work, these random files are obtained combining the information from the JEFF library (fission yields and uncertainties) and the theoretical knowledge from the GEF code. Examples of this method are presented for the main actinides together with their impacts on simple burn-up and decay heat calculations.

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“…The mean and standard deviation of the decay heat is then computed over the 500 calculations. The uncertainties are generally lower than the experimental data (Tobias [9] ,Dickens [10]). …”

Section: Decay Heat Benchmarksmentioning

confidence: 86%

Fission yield covariances for JEFF: A Bayesian Monte Carlo method

et al. 2017

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“…A=95 or 96 and heavy, e.g. A=139 or 140), by odd-even type of the proton and the neutron numbers (odd-odd, odd-even, even-odd and even-even) and by {3-decay Q value (3,5,7,9 and 11 MeV).…”

Section: Calculation and Estimationmentioning

confidence: 99%

Calculation of Beta-Ray Spectra from Individual and Aggregate Fission Products

Tasaka¹,

Miwa²,

Katakura³

et al. 1992

Journal of Nuclear Science and Technology

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The {3-ray spectra of individual fission products were calculated by using the {3-decay data assuming every {3-decay to be allowed transition. For the nuclides without measured decay data the {3-feeding function was evaluated with the gross theory of {3-decay and the {3-ray spectrum was calculated from the function. The measured decay data were also supplemented with the data calculated by the gross theory for the excitation energy range above the highest measured excitation energy level. The {3-ray spectra from aggregate fission products after a burst fission were calculated by using the {3-ray spectrum and the atom number of each fission product nuclide and they were compared with the ones measured for thermal neutron induced fission of 235 U, 239 Pu and 241 Pu at Oak Ridge National Laboratory. The spectrum calculations showed excellent agreement with the measured data at shorter cooling times than 10 s when many short-lived nuclides without measured decay data contributed considerably to the spectrum.

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“…o Oak Ridge spectral expe~iments 5 , 6 in which 23 5u and 239 Pu fuels were irradiated with thermal neutrons for ti~es of 1, 10, . (5 for 239 Pu), and 100 s, and both aggregate fission-product gamma-ray and beta-ray decay-energy spectra were measured for a range of average cooling times from 2.2 s (for the 1-s irradiation time) to 12 000 s (for the 100-s irradiation time).…”

Section: Disclaimermentioning

confidence: 99%

Integral data testing of ENDF/B fission-product data and comparisons of ENDF/B with other fission product data files

LaBauve¹,

England²,

George³

1981

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Three experiments (one from Oak Ridge and two from Los Alamos), in which samples of 235 u and 239 Pu were irradiated with thermal neutrons•and either the total, gamma-ray, or gamma-and beta-ray fission pr_oduct decay-energies were measured as functions of cooling time, were selected for comparisons with calculations made using four different fission product data files. The data files used were (1) the ENDF/B..:..Iv fission product file, (2) the ENDF/B-V fission product file, (3) a file derived by substituting decay energies from JNDC into the ENDF/B-V file, and (4) a file derived by substituting decay-energies and spectra from the UK data file into the ENDF/B-V file. Direct summation calculations and spectral comparisons of the experiments were made using these data files as input, and both types of calculational analyses yielded the same results; namely, all data files are deficient, but the JNDC-ENDF/B-V results for the gamma-and beta-ray•total •decay-energy agree best with experiments. In addition, spectral comparisons with experiment generally indicate that calculated gamma-ray decay-energies are relatively high for early cooling times and small gamma-ray energies; they are low for early cooling times and large gamma-ray energies •. The op-• posite is somewhat the case for the beta-ray decay energies; that• is, the calculations are generally low for small beta-ray energies and high for large energies. I. 1 3.0 X 10-1 1.99 5.4 X 10-2 JNDC &UK 54 XE 147 2.0 X 10-1. 2. 70 2.4 X 10-7 JNDC 55 cs 136 1.9 X 10 1 0.05 6~3 JNDC & UK 55 cs 149 2.4 X 10-1 2.55 0.0 JNDC 56 BA 151 3.3 X 10-1 2.29 o.o JNDC 57 LA 155 1.5 .X w-1 3.20 0.0 JNDC 58 CE 155 5.3 X 10-l 2.04 4.3 x 10-6 JNDC 59 PR 142 /3.8 X 102 o.oo 5.9 JNDC *o denot.es ground, 1 denotes 1st isomeric, 2 denotes znd isomeric states 7 JNDC/ENDF calculations. The multigroup spectra were generated in 150 fine groups from 0 to 7.5 MeV for ENDF/B-IV, each group having a bin width of 0.05 MeV. The bin widths used for the ENDF/B-V and UK_data were also constant (0.05. MeV) from 0.1 to 7.5 MeV, but a finer width (0.01 MeV) was used below 0.1 MeV, which resulted in 158 rather than 150. groups. This was done to better describe the low-energy data (~ ray). available .in ENDF/B~V but not in ENDF/B~IV. Nuclide activities needed in preparing the aggregate fine-group decayenergy (PEFPYD) libraries were obtained from CINDER-10 problems in which thermal pulse irradiations of 23 5u and 239 Pu fuels were specified. These.problems were run using ENDF/B-IV, ENDF/B-V, and JNDC/ENDF fiss~on-product• data. The problem using ENDF/B-IV data for the thermal pulse irradiation of 23 5u was run at sixpoints-per~decade over a cooling time interval from shutdown to I0 13 s. All other problems were run for the same cooling time interval, but at four-pointsper-decade. Note that no separate CINDER-10 problem was rtin using the UK data. Aggregate fine-group fission-product decay libraries (PEFPYD) were then obtained by multiplying the activity and the beta-ray (gamma-ray) energy for each 1. 420E

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Delayed beta- and gamma-ray production due to thermal-neutron fission of /sup 235/U, spectral distributions for times after fission between 2 and 14,000 sec: tabular and graphical data

Cited by 5 publications

References 0 publications

Fission yield covariances for JEFF: A Bayesian Monte Carlo method

Fission yield covariances for JEFF: A Bayesian Monte Carlo method

Calculation of Beta-Ray Spectra from Individual and Aggregate Fission Products

Integral data testing of ENDF/B fission-product data and comparisons of ENDF/B with other fission product data files

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