Fast Neutron Capture Gamma Rays

Bergqvist, I.; Potokar, M.

doi:10.1007/978-1-4613-2940-4_16

Cited by 5 publications

(2 citation statements)

References 20 publications

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“…= ~r~ (n, n') (4) In (4) [26]. Though the error bars, calculated by the Gaussian error propagation formula, are large, the deduced o-,g ,, data are in surprisingly good agreement with the calculated a, g, ,, (E) function.…”

Section: R [Cr G+ Re(n 2 N) + ~R(n Ch) + ~R(n Y) + ~"(N N')]mentioning

confidence: 60%

Neutron induced reaction cross-section of115In around 14 MeV

Csikai

Lantos

Buczkó

et al. 1990

Z. Physik A - Atomic Nuclei

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A systematic investigation was carried out on ~aSIn to determine the contribution of different reactions to the total non-elastic cross-section in the 13.43 and 14.84 MeV incident neutron energy range. All the major components of aNE were measured with exception of the ~g(n, n') cross section. An analytical expression is recommended to estimate the aN~ data as a function of mass number at E, = 14.1 MeV. By the knowledge of aNE, the energy dependence of ag(n, n') could be deduced. The isomeric cross section ratios both for (n, 2n) and (n, n') processes were also determined in the given energy range. The present experiment proves the dependence of am/(~ ~ + a m) ratio on the spin value (I,,) of the isomeric state in the (n, 2n) reaction. Excitation functions of the (n, 2n), (n, n') (n, p) and (n: p, c~) reactions calculated by STAPRE code show good agreement with the experimental results.

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Section: R [Cr G+ Re(n 2 N) + ~R(n Ch) + ~R(n Y) + ~"(N N')]mentioning

confidence: 60%

Neutron induced reaction cross-section of115In around 14 MeV

Csikai

Lantos

Buczkó

et al. 1990

Z. Physik A - Atomic Nuclei

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“…The cross-sections adopted for each of these reactions are shown in figure 1 radiative capture, Radiative capture is not included in the code because it contributes insignificantly to the dose. The data of Bergqvist and Potokar (1979) indicate that the neutron radiative capture cross-section for 0 is about 200 Kb, which is only about O . l o / o of the total cross-section.…”

Section: Monte Carlo Code For Calculating Neutron Dosesmentioning

confidence: 96%

Untitled

Vilaithong¹,

Madey²,

Witten³

et al. 1983

Phys. Med. Biol.

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Absorbed neutron doses in regions outside the treatment volume from negative pion radiotherapy are presented, based on neutron spectral measurements for pions stopping in a tissue-equivalent target. A Monte Carlo neutron transport computer code was developed and used to calculate the absorbed dose as a function of the distance from the centre of the treatment volume. The Monte Carlo code, which is a modification of a neutron detector efficiency code, follows neutrons and gamma rays as they interact with either hydrogen or oxygen nuclei in a phantom. The code includes neutron elastic scattering on both hydrogen and oxygen as well as five inelastic nuclear reactions on oxygen. The recoil charged particles which provide the absorbed dose are considered until the neutron escapes the phantom or its kinetic energy falls below 1 ke V. Calculations of absorbed dose are compared with earlier dose calculations and measurements. Measurements of the neutron spectrum from a tissue-equivalent target indicate that the total kinetic energy carried away by neutrons is about 76 MeV, which is a significantly higher value than that used in earlier estimates of the neutron dose. The calculations presented here suggest that the neutron dose outside large treatment volumes may limit the use of negative pions for some therapeutic applications.

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Experimental Study of Fast Neutron Capture

Cvelbar

Likar

1986

Neutron Induced Reactions

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Fast Neutron Capture Gamma Rays

Cited by 5 publications

References 20 publications

Neutron induced reaction cross-section of115In around 14 MeV

Neutron induced reaction cross-section of115In around 14 MeV

Untitled

Experimental Study of Fast Neutron Capture

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