Measurements of delayed-neutron yields from thermal-neutron-induced fission of 235U, 233U, 239Pu, and 237Np

Борзаков, С. Б.; Андреев, А. Н.; Dermendjiev, E.; Filip, A.; Furman, W.; Panteleev, Ts.; Ruskov, I.; Zamyatnin, Yu. S.; Zeinalov, Sh.S.

doi:10.1134/1.855663

Cited by 15 publications

(10 citation statements)

References 14 publications

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“…The d was revised on the basis of experimental data of Krick and Evans 33) renormalizing them to the thermal value 0.0067, which was obtained by averaging experimental data. [30][31][32] However, the present evaluation is not in agreement with the recent experimental data of Piksaikin et al…”

Section: Uranium (1) U-233contrasting

confidence: 56%

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JENDL Actinoid File 2008

Iwamoto

Nakagawa

Otuka

et al. 2009

Journal of Nuclear Science and Technology

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JENDL Actinoid File 2008 (JENDL/AC-2008) was released in March 2008. It includes nuclear data for neutron-induced reactions for 79 nuclides from Ac (Z ¼ 89) to Fm (Z ¼ 100). The neutron energy range is 10 À5 eV to 20 MeV. Almost all data for 62 actinoids in JENDL-3.3 were revised. New evaluations were performed for 17 nuclides, which have half-lives longer than one day. A new comprehensive theoretical model code CCONE was widely used for the evaluation of cross sections and neutron emission spectra. Thermal cross sections for many nuclides were revised based on experimental data. Resonance parameters were readjusted to reproduce them. Simultaneous evaluations of fission cross sections were performed for six important nuclei. The least-squares fitting code GMA was used for the evaluation of fission cross sections for minor actinoids. In this paper, we present the evaluation methods and results of the JENDL/AC-2008.

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Section: Uranium (1) U-233contrasting

confidence: 56%

“…[30][31][32][33][34][35] For other nuclides, systematics [36][37][38] of d were applied, or the data of JENDL-3.3 were adopted.…”

Section: Number Of Neutrons Per Fissionmentioning

confidence: 99%

JENDL Actinoid File 2008

Iwamoto

Nakagawa

Otuka

et al. 2009

Journal of Nuclear Science and Technology

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“…The number of delayed neutrons per fission d of 233 U was determined on the basis of experimental data. The d value of 0.0067 at the thermal energy was obtained from the experimental data of Borzakov et al, 84) Conant and Palmedo, 85) and Keepin et al 56) In the energy region from 10 keV to 7 MeV, the d value was based on the data of Piksaykin et al, 86) Krick and Evans, 87) and Evans et al 88) As shown in Fig. 8, the present result is largely different from that in JENDL/AC-2008, which was determined by normalizing the data of Krick and Evans to 0.0067 at 0.0253 eV.…”

Section: )mentioning

confidence: 99%

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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“…This is true for all of the available incident neutron energy regions. The data from the sole experiment on the fluctuation of fission γ-ray yields from resonance to resonance does not exclude a (n,γf) reaction channel in the sub-threshold fission of 237 Np [20]. New experiments can be conducted, e.g.…”

Section: Discussionmentioning

confidence: 99%

“…2, [18][19][20]) shows that this fluctuation might be partly explained assuming the existence of a 237 Np(n, γf) reaction channel. In Fig.…”

Section: The (Nγf)-reactionmentioning

confidence: 99%

Neutron induced fission of ²³⁷Np – status, challenges and opportunities

et al. 2018

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Abstract. Nowadays, there is an increased interest in a complete study of the neutroninduced fission of 237 Np. This is due to the need of accurate and reliable nuclear data for nuclear science and technology. 237 Np is generated (and accumulated) in the nuclear reactor core during reactor operation. As one of the most abundant long-lived isotopes in spent fuel ("waste"), the incineration of 237 Np becomes an important issue. One scenario for burning of 237 Np and other radio-toxic minor actinides suggests they are to be mixed into the fuel of future fast-neutron reactors, employing the so-called transmutation and partitioning technology. For testing present fission models, which are at the basis of new generation nuclear reactor developments, highly accurate and detailed neutron-induced nuclear reaction data is needed. However, the EXFOR nuclear database for 237 Np on neutron-induced capture cross-section, σ γ , and fission cross-section, σ f , as well as on the characteristics of capture and fission resonance parameters (Γ γ , Γ f , σ o Γ f , fragments mass-energy yield distributions, multiplicities of neutrons ν n and γ-rays ν γ ), has not been updated for decades.

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Measurements of delayed-neutron yields from thermal-neutron-induced fission of 235U, 233U, 239Pu, and 237Np

Cited by 15 publications

References 14 publications

JENDL Actinoid File 2008

JENDL Actinoid File 2008

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

Neutron induced fission of ²³⁷Np – status, challenges and opportunities

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Measurements of delayed-neutron yields from thermal-neutron-induced fission of 235U, 233U, 239Pu, and 237Np

Cited by 15 publications

References 14 publications

JENDL Actinoid File 2008

JENDL Actinoid File 2008

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

Neutron induced fission of 237Np – status, challenges and opportunities

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Product

Resources

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Neutron induced fission of ²³⁷Np – status, challenges and opportunities