Cross-sections for production of <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si2.svg"><mml:mmultiscripts><mml:mrow><mml:mi>I</mml:mi><mml:mi>n</mml:mi></mml:mrow><mml:none/><mml:none/><mml:mprescripts/><mml:none/><mml:mrow><mml:mn>115</mml:mn><mml:mi>m</mml:mi></mml:mrow></mml:mmultiscripts></mml:math> by quasi-monoenergetic neutrons within 7-20 MeV

Hingu, Akash; Soni, Bhargav; Parashari, Siddharth; Makwana, Rajnikant; Prajapati, P. M.; Vashi, Vibhuti; Mehta, Mayur; Palit, R.; Suryanarayana, S. V.; Nayak, B. K.; Katovsky, Karel; Mukherjee, S.

doi:10.1016/j.radphyschem.2022.110270

Cited by 3 publications

(7 citation statements)

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“…Moreover, there is no experimental cross section available for the 94 Mo(p, γ) 95,g T c reaction in the EXFOR above 2.5 MeV as shown in figure 1 -(c), which reveals the scope of an experimental investigation. The reaction products are radioactive and the activation method [8] can be used to determine the cross section. Theoretical prediction or systematic approach [9] and indirect methods as well can be useful where reaction cross section is not directly possible to measure.…”

Section: Discussionmentioning

confidence: 99%

Astrophysical S factor and reaction rate of ^92,94Mo(p, γ) relevant to the p-process

et al. 2023

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Abstract. Low energy proton capture cross sections on heavy isotopes are necessary for a better understanding of the astrophysical p-process. There are around 35 proton-rich stable isotopes between 74S e and 196Hg which are bypassed by the s- and r- processes. These are commonly referred as p-nuclei whose origin is still not completely understood. In the present study, proton capture reactions are studied on Mo isotopes at astrophysically relevant energies using nuclear modular code TALYS. Astrophysical S factor and reaction rates are also calculated inside a core-collapse supernova. The obtained results are compared with the literature data taken from EXFOR data library. In addition, the effect of different combinations of the nuclear input parameters entering the stellar reaction rate have been investigated.

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Section: Discussionmentioning

confidence: 99%

Astrophysical S factor and reaction rate of ^92,94Mo(p, γ) relevant to the p-process

et al. 2023

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“…( 5), as described in the subsequent section. A comparison of the reference monitor cross-sections from the EXFOR [7] data library and recommended values from the IRDFF-II [20] is shown in Fig. 4.…”

Section: Determination Of Reaction Cross-section and Its Uncertaintymentioning

confidence: 99%

“…The standard data library for neutron monitor reaction cross-section IRDFF-II [20] was used for reference monitor reaction cross-section . As the neutrons generated by the reaction are not monoenergetic but rather have an energy spread, the neutron flux energy spectrum produced by the EPEN [13] code was used to fold the point-wise monitor crosssection in the IRDFF-II library ( ) using the following equation [16]: [7] data library and recommended values from the IRDFF-II library [20].…”

Section: E Cross-sections For Reference Monitor Reactions and Their C...mentioning

confidence: 99%

“…Table 5. IRDFF-II [20] spectrum averaged neutron monitor cross-sections along with fractional uncertainties and correlation and EPEN code computed fractional neutron flux for each neutron energy group. threshold of the first excited state of 7 Be, the neutrons produced from the reaction were contaminated by secondary group of lower energy neutrons produced from the reaction ( MeV).…”

Section: Correction Factor For Low-energy Background Neutronsmentioning

confidence: 99%

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Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Hingu,

Mukherjee,

Parashari

et al. 2024

Chinese Phys. C

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The excitation function of the $\rm {}^{58}Ni ( n, p ){}^{58}Co$ reaction is measured by using the well-established neutron activation technique and $\gamma$-ray spectroscopy. Neutrons in the energy range of 1.7 to 2.7 $\rm MeV$ were generated using the $\rm ^{7}Li(p, n)$ reaction. The neutron flux was measured by using the standard $\rm {}^{115}In ( n, n^{'} ){}^{115m}In$ monitor reaction. The results of neutron spectrum averaged cross-section of $\rm {}^{58}Ni ( n, p ){}^{58}Co$ reactions are compared with existing cross-section data available in the EXFOR data library as well as with various evaluated data libraries like ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0 and CENDL-3.2. Theoretical calculations were performed using the nuclear reaction code TALYS. Various nuclear level density (NLD) models were tested and compared with the present findings. Realistic NLDs are also obtained through the spectral distribution method (SDM). The cross-section results are reported along with the absolute errors by investigating uncertainty propagation, using the covariance technique. The corrections for $\gamma$-ray true coincidence summing, low-energy background neutrons and $\gamma$-ray self attenuation are performed. The experimental cross-section obtained in the present study is consistent with previously published experimental data, evaluated libraries and theoretical calculations carried out using the TALYS code.

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“…The simulation procedure was the same as that discussed in the main section. For the simulation of In sample activation, the cross section of the 115 In(n, n') 115m In reaction was referred from Hingu et al, 25 which had been experimentally summarized.…”

Section: A P P E N D I X B : Va L I Dat I O N O F Fa S T N E U T R O N Smentioning

confidence: 99%

Out‐of‐field dosimetry using a validated PHITS model and computational phantom in clinical BNCT

Kakino,

Hu,

Tanaka

et al. 2023

Medical Physics

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BackgroundThe out‐of‐field radiation dose for boron neutron capture therapy (BNCT), which results from both neutrons and γ‐rays, has not been extensively evaluated. To safely perform BNCT, the neutron and γ‐ray distributions inside the treatment room and the whole‐body dose should be evaluated during commissioning. Although, certain previous studies have evaluated the whole‐body dose in the clinical research phase, no institution providing BNCT covered by health insurance has yet validated the neutron distribution inside the room and the whole‐body dose.PurposeTo validate the Monte Carlo model of the BNCT irradiation room extended for the whole‐body region and evaluate organ‐at‐risk (OAR) doses using the validated model with a human‐body phantom.MethodsFirst, thermal neutron distribution inside the entire treatment room was measured by placing Au samples on the walls of the treatment room. Second, neutron and gamma‐ray dose‐rate distributions inside a human‐body water phantom were measured. Both lying and sitting positions were considered. Bare Au, Au covered by Cd (Au+Cd), In, Al, and thermoluminescent dosimeters were arranged at 11 points corresponding to locations of the OARs inside the phantom. After the irradiation, γ‐ray peaks emitted from the samples were measured by a high‐purity germanium detector. The measured counts were converted to the reaction rate per unit charge of the sample. These measurements were compared with results of simulations performed with the Particle and Heavy Ion Transport code System (PHITS). A male adult mesh‐type reference computational phantom was used to evaluate OAR doses in the whole‐body region. The relative biological effectiveness (RBE)‐weighted doses and dose‐volume histograms (DVHs) for each OAR were evaluated. The median dose (D50%) and near‐maximum dose (D2%) were evaluated for 14 OARs in a 1‐h‐irradiation process. The evaluated RBE‐weighted doses were converted to equivalent doses in 2 Gy fractions.ResultsExperimental results within 60 cm from the irradiation center agreed with simulation results within the error bars except at ±20, 30 cm, and those over 70 cm corresponded within one digit. The experimental results of reaction rates or γ‐ray dose rate for lying and sitting positions agreed well with the simulation results within the error bars at 8, 4, 11, 7 and 7, 4, 7, 6, 5, 6 out of 11 points, respectively, for Au, Au+Cd, In, Al, and TLD. Among the detectors, the discrepancies in reaction rates between experiment and simulation were most common for Au+Cd, but were observed randomly for measurement points (brain, lung, etc.). The experimental results of γ‐ray dose rates were systematically lower than simulation results at abdomen and waist regions for both positions. Extending the PHITS model to the whole‐body region resulted in higher doses for all OARs, especially 0.13 Gy‐eq increase for D50% of the left salivary gland.ConclusionThe PHITS model for clinical BNCT for the whole‐body region was validated, and the OAR doses were then evaluated. Clinicians and medical physicists should know that the out‐of‐field radiation increases the OAR dose in the whole‐body region.

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Cross-sections for production of In115m by quasi-monoenergetic neutrons within 7-20 MeV

Cited by 3 publications

References 30 publications

Astrophysical S factor and reaction rate of ^92,94Mo(p, γ) relevant to the p-process

Astrophysical S factor and reaction rate of ^92,94Mo(p, γ) relevant to the p-process

Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Out‐of‐field dosimetry using a validated PHITS model and computational phantom in clinical BNCT

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Cross-sections for production of In115m by quasi-monoenergetic neutrons within 7-20 MeV

Cited by 3 publications

References 30 publications

Astrophysical S factor and reaction rate of 92,94Mo(p, γ) relevant to the p-process

Astrophysical S factor and reaction rate of 92,94Mo(p, γ) relevant to the p-process

Investigation of 58Ni (n, p)58Co reaction cross-section with covariance analysis*

Out‐of‐field dosimetry using a validated PHITS model and computational phantom in clinical BNCT

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Product

Resources

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Astrophysical S factor and reaction rate of ^92,94Mo(p, γ) relevant to the p-process

Astrophysical S factor and reaction rate of ^92,94Mo(p, γ) relevant to the p-process

Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*