On the number of neutrons emitted by U235 fission fragments

Apalin, V.F.; Gritsyuk, Yu.N.; Kutikov, I.E.; Lebedev, V. I.; Mikaelyan, L.A.

doi:10.1016/0029-5582(64)90143-9

Cited by 45 publications

(8 citation statements)

References 11 publications

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“…As the test of our result we compared pre-PFN emission mass yield curves, obtained from the common data set, analyzed using ν(A) data from our measurements and from the literature Ref. [8]. As it was mentioned earlier in this report, in data analysis procedure we used linear calibration procedure with two parameters: the light FF average kinetic energy (100.6 MeV) and the TKE (170.5 MeV).…”

Section: Resultsmentioning

confidence: 99%

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Prompt fission neutron investigation in ²³⁵U(n_th,f) reaction

et al. 2017

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Abstract. The prompt neutron emission in thermal neutron induced fission of 235 U has been investigated applying digital signal electronics. The goal was to compare the results of this digital data acquisition and digital signal processing analysis to the results of the pioneering work of Apalin et al. Using a twin Frisch grid ionization chamber for the fission fragment detection and a NE213 equivalent neutron detector in total about 10 6 neutron coincidences have been registered. The fission fragment kinetic energy, mass and angular distribution has been investigated along with prompt neutron time of flight and pulse shape using a six channel synchronous waveform digitizer with sampling frequency of 250 MHz and 12 bit resolution. The signals have been analyzed using digital pulse processing algorithms, developed by authors. The thermal neutron beam was transported from the IBR-2 reactor to the target with bent mirror neutron guide.

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Section: Resultsmentioning

confidence: 99%

“…One was obtained using theν(A) measured in our experiment, another one with ν(A) was taken from Ref. [8]. Mass yield curve from Ref.…”

Section: Resultsmentioning

confidence: 99%

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Prompt fission neutron investigation in ²³⁵U(n_th,f) reaction

et al. 2017

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“…APALIN'S [16] a39 Pu neutron curve was used for correction in case of 341 Am also. The primary fragment energy was converted into the total kinetic energy release using the Eq.…”

Section: Where E P and ê S Are The Average Kinetic Energies Of The Prmentioning

confidence: 99%

Recoil Ranges and Kinetic Energy Distribution in the Reactor Neutron Induced Fission of ²⁴¹ Am

Prakash

Manohar²,

Dange

et al. 1972

Radiochimica Acta

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Recoil ranges in aluminium have been determined for seventeen fission products, from reactor neutron induced fission of M1 Am. From the recoil range data, kinetic energy distribution as a function of fragment mass has been obtained, using three different range-energy equations. It has been found that both in magnitude as well as the shape of the kinetic energy distribution is dependent on the range-energy equations. Using the kinetic energy data obtained in the present work, deformation of fission fragments has been calculated. ZusammenfassungDie Rückstoßreichweiten in Aluminium sind für siebzehn Spaltprodukte durch die im Reaktor ausgelöste Spaltung von 241 Am bestimmt worden. Aus den ermittelten Rückstoß-reichweiten ist die Verteilung der kinetischen Energie in Abhängigkeit von der Masse der Bruchstücke ermittelt worden. Dazu dienten drei verschiedene Reichweite-Energie-Gleichungen. Es wurde festgestellt, daß die Verteilung der kinetischen Energie sowohl größenordnungsmäßig als auch in ihrer Form von den Reichweite-Energie-Gleichungen abhängt. Mit Hilfe der in dieser Arbeit ermittelten Daten über die kinetische Energie wurde die Deformation der Spaltbruchstücke errechnet. RésuméOn a déterminé les parcours de recul en aluminium valables pour 17 produits de fission provenant de la fission d'Am-241 induite par les neutrons du réacteur. Les valeurs spécifiant le parcours de recul ont fourni la distribution de l'énergie ciné-tique en fonction de la masse fragmentaire utilisant trois différentes équations parcours/énergie. On a trouvé que l'ordre de grandeur ainsi que la forme de distribution de l'énergie cinétique dépendent des équations parcours/énergie. Utilisant les valeurs de l'énergie cinétique obtenues dans ce travail on a calculé la déformation des fragments de fission.

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“…2 are included for reference and show determinations of v(m) for the thermal-neutron fission of 233 U. 8 ' 9 Since the compound nucleus 234 U in this case is different from ours ( 234 Np), no direct comparison with our data should be made.…”

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confidence: 91%

Prompt Neutrons from Fission ofU233by 8.5- and 13.0-MeV Protons

Burnett¹,

Ferguson²,

Plášil³

et al. 1968

Phys. Rev. Lett.

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A comparison of the number of neutrons emitted as a function of fragment mass is reported for 8.5-and 13.0-MeV proton-induced fission of 233 U. Results indicate that the excitation energies of the light fragments do not change appreciably, while those of the heavy fragments increase with increasing incident energy. The increase in fragment excitation for masses of ~132 amu (Zs 50, iVs 82) is significantly greater than that in compound-nucleus excitation and is accompanied by a decrease in fragment kinetic energy.

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On the number of neutrons emitted by U235 fission fragments

Cited by 45 publications

References 11 publications

Prompt fission neutron investigation in ²³⁵U(n_th,f) reaction

Prompt fission neutron investigation in ²³⁵U(n_th,f) reaction

Recoil Ranges and Kinetic Energy Distribution in the Reactor Neutron Induced Fission of ²⁴¹ Am

Prompt Neutrons from Fission ofU233by 8.5- and 13.0-MeV Protons

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On the number of neutrons emitted by U235 fission fragments

Cited by 45 publications

References 11 publications

Prompt fission neutron investigation in 235U(nth,f) reaction

Prompt fission neutron investigation in 235U(nth,f) reaction

Recoil Ranges and Kinetic Energy Distribution in the Reactor Neutron Induced Fission of 241 Am

Prompt Neutrons from Fission ofU233by 8.5- and 13.0-MeV Protons

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Prompt fission neutron investigation in ²³⁵U(n_th,f) reaction

Prompt fission neutron investigation in ²³⁵U(n_th,f) reaction

Recoil Ranges and Kinetic Energy Distribution in the Reactor Neutron Induced Fission of ²⁴¹ Am