Experimental Determination of the Response of Four Bonner Sphere Sets to Thermal Neutrons

Thomas, David J.; Alevra, A.; Hunt, James B.; Schraube, H.

doi:10.1093/oxfordjournals.rpd.a082312

Cited by 29 publications

(14 citation statements)

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“…In all subsequent comparisons, the reference H * (10) value is given by the HMGU extended-range BSS system since the latter was previously calibrated with monoenergetic neutron beams of up to 387 MeV (Ref. 22), and H * (10) measurements were made with this detector set at all positions (1)(2)(3)(4). One should finally note that both BSS systems involve a dead time factor below 40 µs implicating a negligible error.…”

Section: C1 Bonner Sphere Systemsmentioning

confidence: 99%

Measurement of stray radiation within a scanning proton therapy facility: EURADOS WG9 intercomparison exercise of active dosimetry systems

et al. 2015

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Section: C1 Bonner Sphere Systemsmentioning

confidence: 99%

Measurement of stray radiation within a scanning proton therapy facility: EURADOS WG9 intercomparison exercise of active dosimetry systems

et al. 2015

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“…The data from these calculations for irradiation with a 252 Cf source show very close agreement with the measurements performed for this project (Table 1). The evidence from previous measurements is that the gas pressure tends to be a little lower (Thomas et al, 1994): on average the thermal neutron response of an SP9 counter was found to be about 2.65 cm 2 corresponding to a pressure of roughly 191 kPa. The measured values varied from 2.53 to 2.74 cm 2 , a range of roughly 8.3% in the thermal neutron response.…”

Section: 233mentioning

confidence: 85%

Practical implications of neutron survey instrument performance

Tanner¹,

Bartlett²,

Hager

et al. 2004

Radiation Protection Dosimetry

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Improvements have been made to the Monte Carlo modelling used to calculate the response of the neutron survey instruments most commonly used in the UK, for neutron energies up to 20 MeV. The improved modelling of the devices includes the electronics and battery pack, allowing better calculations of both the energy and angle dependence of response. These data are used to calculate the response of the instruments in rotationally and fully isotropic, as well as unidirectional fields. Experimental measurements with radionuclide sources and monoenergetic neutron fields have been, and continue to be made, to test the calculated response characteristics. The enhancements to the calculations have involved simulation of the sensitivity of the response to variations in instrument manufacture, and will include the influence of the user and floor during measurements. The practical implications of the energy and angle dependence of response, variations in manufacture, and the influence of the user are assessed by folding the response characteristics with workplace energy and direction distributions.

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“…A bare 3 He proportional counter without any surrounding material is also used as the 18th measuring channel. This system enables accurate measurements of neutron fluence spectra, Ф(E), and ambient dose equivalent, H * (10), values, since the fluence response functions (HEMA99) of all spheres with 3 He proportional counter in their center were calculated by means of Monte Carlo (MC) simulations [5,6] and experimentally validated at 13 neutron energies between thermal and 14.8 MeV [7,8] as well as with quasi-mono-energetic neutron fields with peak energies at 244 MeV and 387 MeV [9].…”

Section: Extended Range Bonner Sphere Spectrometermentioning

confidence: 99%

Neutron spectrometry and dosimetry in 100 and 300 MeV quasi-mono-energetic neutron field at RCNP, Osaka University, Japan

et al. 2017

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This paper describes the results of neutron spectrometry and dosimetry measurements using an Extended Range Bonner Sphere Spectrometer (ERBSS) with 3 He proportional counter performed in quasi-mono-energetic neutron fields at the ring cyclotron facility of the Research Center for Nuclear Physics (RCNP), Osaka University, Japan. Using 100 MeV and 296 MeV proton beams, neutron fields with nominal peak energies of 96 MeV and 293 MeV were generated via 7 Li(p,n) 7 Be reactions. Neutrons produced at 0° and 25° emission angles were extracted into the 100 m long time-of-flight (TOF) tunnel, and the energy spectra were measured at a distance of 35 m from the target. To deduce the corresponding neutron spectra from thermal to the nominal maximum energy, the ERBSS data were unfolded using the MSANDB unfolding code. At high energies, the neutron spectra were also measured by means of the TOF method using NE213 organic liquid scintillators. The results are discussed in terms of ambient dose equivalent, H*(10), and compared with the readings of other instruments operated during the experiment.

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Experimental Determination of the Response of Four Bonner Sphere Sets to Thermal Neutrons

Cited by 29 publications

References 0 publications

Measurement of stray radiation within a scanning proton therapy facility: EURADOS WG9 intercomparison exercise of active dosimetry systems

Measurement of stray radiation within a scanning proton therapy facility: EURADOS WG9 intercomparison exercise of active dosimetry systems

Practical implications of neutron survey instrument performance

Neutron spectrometry and dosimetry in 100 and 300 MeV quasi-mono-energetic neutron field at RCNP, Osaka University, Japan

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