Thermal neutron radiative capture cross-section of<sup>186</sup>W(n, γ)<sup>187</sup>W reaction

Tan, Vuong Huu

doi:10.1088/1742-6596/726/1/012004

J. Phys.: Conf. Ser.

2016

DOI: 10.1088/1742-6596/726/1/012004

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Thermal neutron radiative capture cross-section of¹⁸⁶W(n, γ)¹⁸⁷W reaction

Vuong Huu Tan¹

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Cited by 3 publications

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“…Experimental set up at the neutron beam channel No.2 of DRR at the DRR The absolute detection efficiency curve of the HPGe detector for standard foils at 5 cm from the detector end-capThe thermal neutron flux is determined from the activity of the Vanadium foil as follows(Akhlaghi et al 2013;Tan & Son 2016;Yamamoto et al 2002),…”

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confidence: 99%

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Measurement of Neutron Flux and Gamma Dose Rate Distribution Inside a Water Phantom for Boron Neutron Capture Therapy Study at Dalat Research Reactor

Trinh¹,

Pham²,

Nhan³

et al. 2019

JSM

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Exposure dose rate to the tumor and surrounding cells during neutron beam irradiation in Boron Neutron Capture Therapy (BNCT) comes not only from heavy charged particles produced from the 10 B(n,α) 7 Li nuclear reaction, but also from neutron-induced reactions with other biological elements in living tissue, as well as from gamma rays leaked from the reactor core. At Dalat Research Reactor, Vietnam, the neutron and gamma dose rate distribution inside a water phantom were measured by using activation method and Thermoluminescent Dosimeter (TLD) detector, respectively. The results showed that effective thermal neutron dose rate along the center line of the water phantom had a maximum value of 479 mSv h -1 at 1 cm in phantom and then decreases rapidly to 4.87 mSv h -1 at 10 cm. The gamma dose rate along the center line of the water phantom also reach its maximum of 4.31 mSv h -1 at 1 cm depth and decreases to 1.16 mSv h -1 at 10 cm position. The maximum biological tumor dose rate was 1.74 Gy-eq h -1 , not high enough to satisfy the treatment requirement of brain tumors. However, the results of this work are important in supporting of BNCT study in the upcoming stages at Dalat Research Reactor. ABSTRAK Kadar dos pendedahan kepada tumor dan sel sekitarnya semasa pancaran sinaran neutron dalam Terapi Boron NeutronTertawan (BNCT) datang bukan sahaja daripada zarah berat bercas yang dihasilkan daripada tindak balas nuklear 10 B(n,α) 7 Li, tetapi juga daripada tindak balas neutron-teraruh daripada unsur biologi lain dalam tisu hidup, selain daripada sinar gama yang bocor daripada teras reaktor. Di Reaktor Penyelidikan Dalat, Vietnam, kadar pengagihan dos neutron dan gama dalam fantom air diukur masing-masing menggunakan kaedah pengaktifan dan pengesan Thermoluminescent Dosimeter (TLD). Keputusan menunjukkan bahawa kadar dos haba neutron yang berkesan sepanjang garis tengah fantom air mempunyai nilai maksimum 479 mSv h -1 pada 1 cm dalam phantom dan kemudian menurun dengan pantas kepada 4.87 mSv h -1 pada 10 cm. Kadar dos gama sepanjang garis tengah fantom air juga mencapai tahap maksimum 4.31 mSv h -1 pada kedalaman 1 cm dan menurun ke 1.16 mSv h -1 pada kedudukan 10 cm. Kadar dos maksimum tumor biologi adalah 1.74 Gy-eq h -1 namun tidak cukup tinggi untuk memenuhi keperluan rawatan tumor otak. Walau bagaimanapun, keputusan kajian ini adalah penting dalam menyokong pengajian BNCT pada peringkat akan datang di Reaktor Penyelidikan Dalat. Kata kunci: BNCT; fantom air; fluks haba neutron; kadar dos; pengesan TLD

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“…Parameters of the thermal neutron beam line at outer of the horizontal channel No. 2 of the DRR(Tan & Son 2016) …”

mentioning

confidence: 99%

Measurement of Neutron Flux and Gamma Dose Rate Distribution Inside a Water Phantom for Boron Neutron Capture Therapy Study at Dalat Research Reactor

Trinh¹,

Pham²,

Nhan³

et al. 2019

JSM

View full text Add to dashboard Cite

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Thermal neutron capture cross-section and resonance integral measurements of 186W(n,γ)187W reaction using the thermal column neutron source at the Dalat research reactor

Tu Anh,

Son,

Thuy

et al. 2023

Annals of Nuclear Energy

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Neutron capture reaction cross section measurement for iodine nucleus with detailed uncertainty quantification

et al. 2021

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Thermal neutron radiative capture cross-section of¹⁸⁶W(n, γ)¹⁸⁷W reaction

Cited by 3 publications

References 7 publications

Measurement of Neutron Flux and Gamma Dose Rate Distribution Inside a Water Phantom for Boron Neutron Capture Therapy Study at Dalat Research Reactor

Measurement of Neutron Flux and Gamma Dose Rate Distribution Inside a Water Phantom for Boron Neutron Capture Therapy Study at Dalat Research Reactor

Thermal neutron capture cross-section and resonance integral measurements of 186W(n,γ)187W reaction using the thermal column neutron source at the Dalat research reactor

Neutron capture reaction cross section measurement for iodine nucleus with detailed uncertainty quantification

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Thermal neutron radiative capture cross-section of186W(n, γ)187W reaction

Cited by 3 publications

References 7 publications

Measurement of Neutron Flux and Gamma Dose Rate Distribution Inside a Water Phantom for Boron Neutron Capture Therapy Study at Dalat Research Reactor

Measurement of Neutron Flux and Gamma Dose Rate Distribution Inside a Water Phantom for Boron Neutron Capture Therapy Study at Dalat Research Reactor

Thermal neutron capture cross-section and resonance integral measurements of 186W(n,γ)187W reaction using the thermal column neutron source at the Dalat research reactor

Neutron capture reaction cross section measurement for iodine nucleus with detailed uncertainty quantification

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Product

Resources

About

Thermal neutron radiative capture cross-section of¹⁸⁶W(n, γ)¹⁸⁷W reaction