Fission-energy release for 16 fissioning nuclides. Final report

Sher, R.

doi:10.2172/6614291

Cited by 17 publications

(15 citation statements)

References 2 publications

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“…In JENDL-4.0, a completely new evaluation was performed for Zn isotopes, 64;65;66;67;68;70 Zn, by using available experimental data in the energy range from 10 À5 eV to 20 MeV. The cross section data of unstable 65 Zn were also evaluated because of a relatively long half-life of 244.06 d.…”

Section: Fission Productsmentioning

confidence: 99%

“…This value is about 5 orders of magnitude smaller than the capture cross section. As for 65 Zn for which no resolved resonances have been reported, the capture and ðn; Þ reaction cross sections at the thermal energy were evaluated to be 64 and 2 b, respectively, from the recommended values. 109) In the fast neutron region, the cross sections were evaluated with the CCONE code.…”

Section: )mentioning

confidence: 99%

“…Problems with 63; 65 Cu data in JENDL-3.3 were pointed out from the benchmark analyses 165) of fast reactors with copper reflectors. As a result, the total cross sections of both isotopes were revised in the energy region from 50 keV to 1.1 MeV, where the data were taken from the measurements of Pandey et al 166) Moreover, the elastic angular distributions for both isotopes were calculated with the POD code using the CC OMPs obtained by Kunieda et al…”

Section: (8) Coppermentioning

confidence: 99%

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JENDL-4.0: A New Library for Nuclear Science and Engineering

Shibata

Iwamoto

Nakagawa

et al. 2011

J. Nucl. Sci. Technol.

175

152

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The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the improvements of fission product and minor actinoid data. Two nuclear model codes were developed in order to evaluate the cross sections of fission products and minor actinoids. Coupled-channel optical model parameters, which can be applied to wide mass and energy regions, were obtained for nuclear model calculations. Thermal cross sections of actinoids were carefully examined by considering experimental data or by the systematics of neighboring nuclei. Most of the fission cross sections were derived from experimental data. A simultaneous evaluation was performed for the fission cross sections of important uranium and plutonium isotopes above 10 keV. New evaluations were performed for the thirty fissionproduct nuclides that had not been contained in the previous library JENDL-3.3. The data for light elements and structural materials were partly reevaluated. Moreover, covariances were estimated mainly for actinoids. The new library was released as JENDL-4.0, and the data can be retrieved from the Web site of the JAEA Nuclear Data Center.

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Section: Fission Productsmentioning

confidence: 99%

Section: )mentioning

confidence: 99%

Section: (8) Coppermentioning

confidence: 99%

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JENDL-4.0: A New Library for Nuclear Science and Engineering

Shibata

Iwamoto

Nakagawa

et al. 2011

J. Nucl. Sci. Technol.

175

152

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“…Sher and Beck found that, within the nuclei they examined, the fraction of the decay energy going to betas, neutrinos and delayed gammas was independent of the identity of the compound nucleus [8]. Since the characteristics of β decay are unique to the properties of the fission products rather than the fissioning compound nucleus itself, this result is not surprising.…”

Section: Model Descriptionmentioning

confidence: 93%

“…We follow the nomenclature of Sher and Beck [8], comprising nine specific components of the energy release. They are as follows:…”

Section: Model Descriptionmentioning

confidence: 99%

Generalized Energy-Dependent Q Values for Fission

Vogt¹

2011

J. Korean Phy. Soc.

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Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes

Zou

et al. 2019

Int J Energy Res

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Summary The thorium‐uranium (Th‐U) fuel cycle is considered as a potential approach to ensure a long‐term supply of nuclear fuel. Small modular molten salt reactor (SMMSR) is regarded as one of the candidate reactors for Th utilization, since it inherits the merits of both MSR and small modular reactor. The Th utilization in a 220‐MWe SMMSR with the once‐through fuel cycle mode is investigated first. Then, the SMMSR with batch and online fuel processing modes is investigated second for comparison, considering the progressive development of fuel reprocessing technology. To keep a negative temperature reactivity feedback coefficient (TRC), a configuration for fuel salt volume fraction (SVF) equal to 15%, with a mixed fuel of low enriched uranium (LEU) and thorium at an operation time of 5 years is recommended for the once‐through mode, corresponding to the Th energy contribution (ThEC) of 37.6% and natural U and Th utilization efficiency (UE) of 0.51%. Considering the solubility limit of heavy nuclide (HN) proportion (below 18.0 mol%) in the fuel salt, the total operation time of the SMMSR shall be less than 50 years for the batch reprocessing mode with a 5‐year reprocessing interval time. In this case, the ThEC and UE can be improved to about 47.4% and 0.99%, respectively. Finally, the Th utilization and fuel sustainability are analyzed at a lifetime of 50 years for the online reprocessing fuel cycle mode, including both the only online fission products (FPs) removing scheme and the fuel transition scheme from LEU to 233U. For the former scheme, the ThEC and UE can be further improved to 58.6% and 1.52%, respectively. For the latter scheme, 233Pa is extracted continuously from the core to breed and store 233U. If a total reactor lifetime of 50 years is assumed, the operation time using LEU as starting and feeding fuel for 6 years is required, and the bred 233U during this 6‐year operation can start and maintain the reactor criticality for the remaining 44 years. In this case, the ThEC is improved significantly to 89.1% corresponding to a UE of 2.74%.

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Fission-energy release for 16 fissioning nuclides. Final report

Cited by 17 publications

References 2 publications

JENDL-4.0: A New Library for Nuclear Science and Engineering

JENDL-4.0: A New Library for Nuclear Science and Engineering

Generalized Energy-Dependent Q Values for Fission

Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes

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