Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications

Akan, Zafer; Türkmen, Mehmet; Çakır, Tahir; Reyhancan, İskender Atilla; Çolak, Üner; Okka, Muhittin; Kızıltaş, Sahip

doi:10.1016/j.apradiso.2015.02.014

Cited by 10 publications

(6 citation statements)

References 24 publications

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“…Figure 2 shows the geometry design of Polyethylene/ Cerrobend collimator. [20] Before installing the collimator, the initial step must be used to measure the neutron flux produced by using neutron activation analysis (Au-Cd Foils). Then the results from the neutron activation analysis was used to verified using MCNP (Monte Carlo Neutron Particle) simulation.…”

Section: Bnct Historical and Reviewmentioning

confidence: 99%

“…Then the results from the neutron activation analysis was used to verified using MCNP (Monte Carlo Neutron Particle) simulation. The used of polyethylene as collimator is good to reduce the slow neutron while the Cerrobend is more efficient to provide and produces the epithermal neutron [20]. Despite the use of research reactor as the neutron source for BNCT, the accelerator facility also is recognized as a neutron source.…”

Section: Bnct Historical and Reviewmentioning

confidence: 99%

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Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

Shalbi

Sazali

Salleh

2021

ARFMTS

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The thermal column at the TRIGA PUSPATI (RTP) research reactor can produce thermal neutron. However, the optimization on the thermal neutron flux produced should be performed to gain a sufficient thermal neutron for boron neutron capture therapy purpose. Thus, the objective of this review is to optimize the thermal neutron flux by designing the collimator with different materials at the thermal column. In order to fulfil the requirement, set by the IAEA standard, the study of Boron Neutron Capture Therapy (BNCT) around the world was being reviewed to study the suitable measurement, material, design, and modification for BNCT at the thermal column of TRIGA MARK-II, Malaysia. Initially, the BNCT mechanisms and history was review. Then, this paper review on the design and modifications for BNCT purpose around the world. Based on this review, suitable material and design can be used for the BNCT in Malaysia. Moreover, this paper also reviews the current status of BNCT at the RTP with the measurement of the thermal neutron flux was conducted along the thermal column at 250 kW. The thermal column of RTP was divided into 3 phases (Phase 1, Phase 2 and Phase 3) so that an accurate measurement can be obtained by using gold foil activation method. This value was used as a benchmark for the neutron flux produced from the thermal column. The reviewed demonstrated that the final thermal neutron flux produced was significantly for BNCT purpose.

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Section: Bnct Historical and Reviewmentioning

confidence: 99%

Section: Bnct Historical and Reviewmentioning

confidence: 99%

Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

Shalbi

Sazali

Salleh

2021

ARFMTS

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“…For 10B nuclear decay efficiency calculation, the 2.5 ppm 10B-DG in the 5 ml distilled water were irradiated with 8.074 gy/hr neutron flux in a duration of 80 min in the previously modified radial port of Istanbul Technical University TRIGA MARK II nuclear reactor (13). Nuclear decay time and efficiency of 10B were calculated due to ICP-OES 10B analysis in the samples (Figure 1).…”

Section: Neutron Irradiation Time and Dose Calculationsmentioning

confidence: 99%

“…Our study group have newly developed a novel 10B carrier (2R)-4,5,6-trihydroxy-2-(hydroxymethyl)tetrahydro-2H-pyran-3-yl)boronic acid (BDG). Biodistrubiton analyse result has shown that that 10B succesfully and specifically accumulated in the tumor tissue by the 10BDG and had also antiproliferative and antiapoptotic effects against tumor cells (12,13). In the present in vivo study, we assessed the efficacy of BDG as a novel 10B carrier and the success of BNCT application by using BDG in prostate cancer (PCa) model in rats.…”

Section: Introductionmentioning

confidence: 97%

The treatment of metastatic prostate carcinoma with BNCT in the ITU TRIGA MARKII reactor on rat model

Akan¹,

Özdemir²,

Oto³

et al. 2016

Med Sci and Discov

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Objective: The delivery of curative radiotherapy is commonly has the potential of serious side effects. These side effects still remain dose-limiting factor for external beam radiotherapy and as also curative treatment of prostate cancer (PCa). New treatment alternatives, such as BNCT, are investigated to eliminate these limitations and to improve the therapeutic efficiency of radiation on tumour cells including prostate cancer. In this study, we investigated the efficiency of BNCT application by using our novel 10B carrier that was called as 10B-DG on PCa using an in vivo mouse xenograft model. Material and Methods:PCa bearing Copenhagen rats (CRs) were used in this experimental animal study. A total of 12 CRs at the age of 2 months were used in this experimental animal study. MAT-LyLu PCa cells were injected subcutaneously into the peritoneal cavity of rats to create PCa model. The samples were divided into 4 groups: As, control, neutron irradiated, 10B-DG and 10B-DG + neutron irradiated group. 10BDG was administrated to tumour bearing rats and rats were exposed to 8.074 gy/hr thermal and epithermal. Tumour sizes were regularly measured by microtome and PET scan along 20 days. Results:The results have shown that the tumor growth were regressed just in 10B-DG + neutron irradiated group. In addition that, PET-CT scan results revealed that 18FDG uptake was stopped in the BNCT treated group due to metabolic inactivation of ablated tumor tisue. Conclusion:This study revealed that BNCT treatment can be successfully performed by using our novel 10B carrier 10BDG in the management of PCa. We suppose that this novel 10B carrier can take place as a safe and effective agent in routine clinical practice of BNCT.

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“…In general, the magnitude of neutrons flux for a successful BNCT treatment should be in the order of 10 9 -10 12 n cm -2 s -1 (Akan et al 2015). To achieve this neutron flux, accelerators or research reactors are employed.…”

Section: Introductionmentioning

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

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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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Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications

Cited by 10 publications

References 24 publications

Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

Measurement of Neutron Flux at Thermal Column Using Gold Foil Activation Analysis and TLD Detector: Technical Review

The treatment of metastatic prostate carcinoma with BNCT in the ITU TRIGA MARKII reactor on rat model

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

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