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Nelson BJB, Wilson J, Andersson JD, Wuest F. Theranostic Imaging Surrogates for Targeted Alpha Therapy: Progress in Production, Purification, and Applications. Pharmaceuticals (Basel) 2023; 16:1622. [PMID: 38004486 PMCID: PMC10674391 DOI: 10.3390/ph16111622] [Citation(s) in RCA: 1] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 10/11/2023] [Revised: 11/08/2023] [Accepted: 11/14/2023] [Indexed: 11/26/2023] Open
Abstract
This article highlights recent developments of SPECT and PET diagnostic imaging surrogates for targeted alpha particle therapy (TAT) radiopharmaceuticals. It outlines the rationale for using imaging surrogates to improve diagnostic-scan accuracy and facilitate research, and the properties an imaging-surrogate candidate should possess. It evaluates the strengths and limitations of each potential imaging surrogate. Thirteen surrogates for TAT are explored: 133La, 132La, 134Ce/134La, and 226Ac for 225Ac TAT; 203Pb for 212Pb TAT; 131Ba for 223Ra and 224Ra TAT; 123I, 124I, 131I and 209At for 211At TAT; 134Ce/134La for 227Th TAT; and 155Tb and 152Tb for 149Tb TAT.
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Affiliation(s)
- Bryce J. B. Nelson
- Department of Oncology, University of Alberta, 11560 University Ave., Edmonton, AB T6G 1Z2, Canada; (B.J.B.N.); (J.W.); (J.D.A.)
| | - John Wilson
- Department of Oncology, University of Alberta, 11560 University Ave., Edmonton, AB T6G 1Z2, Canada; (B.J.B.N.); (J.W.); (J.D.A.)
| | - Jan D. Andersson
- Department of Oncology, University of Alberta, 11560 University Ave., Edmonton, AB T6G 1Z2, Canada; (B.J.B.N.); (J.W.); (J.D.A.)
- Edmonton Radiopharmaceutical Center, Alberta Health Services, 11560 University Ave., Edmonton, AB T6G 1Z2, Canada
| | - Frank Wuest
- Department of Oncology, University of Alberta, 11560 University Ave., Edmonton, AB T6G 1Z2, Canada; (B.J.B.N.); (J.W.); (J.D.A.)
- Cancer Research Institute of Northern Alberta, University of Alberta, Edmonton, AB T6G 2E1, Canada
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Huang Y, Zu T, Cao L, Wu H. Capability of processing the GNDS format evaluated nuclear data in NECP-Atlas for neutronics calculations. Progress in Nuclear Energy 2022. [DOI: 10.1016/j.pnucene.2022.104293] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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Nelson BJB, Ferguson S, Wuest M, Wilson J, Duke MJM, Richter S, Soenke-Jans H, Andersson JD, Juengling F, Wuest F. First In Vivo and Phantom Imaging of Cyclotron-Produced 133La as a Theranostic Radionuclide for 225Ac and 135La. J Nucl Med 2022; 63:584-590. [PMID: 34385334 PMCID: PMC8973294 DOI: 10.2967/jnumed.121.262459] [Citation(s) in RCA: 14] [Impact Index Per Article: 7.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [MESH Headings] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 04/18/2021] [Revised: 07/16/2021] [Indexed: 01/18/2023] Open
Abstract
Theranostic isotope pairs have gained recent clinical interest because they can be labeled to the same tracer and applied for diagnostic and therapeutic purposes. The goals of this study were to investigate cyclotron production of clinically relevant 133La activities using natural and isotopically enriched barium target material, compare fundamental PET phantom imaging characteristics of 133La with those of common PET radionuclides, and demonstrate in vivo preclinical PET tumor imaging using 133La-PSMA-I&T. Methods:133La was produced on a 24-MeV cyclotron using an aluminum-indium sealed target with 150-200 mg of isotopically enriched 135BaCO3, natBaCO3, and natBa metal. A synthesis unit performed barium/lanthanum separation. DOTA, PSMA-I&T, and macropa were radiolabeled with 133La. Derenzo and National Electrical Manufacturers Association phantom imaging was performed with 133La, 132La, and 89Zr and compared with 18F, 68Ga, 44Sc, and 64Cu. In vivo preclinical imaging was performed with 133La-PSMA-I&T on LNCaP tumor-bearing mice. Results: Proton irradiations for 100 µA·min at 23.3 MeV yielded 214 ± 7 MBq of 133La and 28 ± 1 MBq of 135La using 135BaCO3, 59 ± 2 MBq of 133La and 35 ± 1 MBq of 135La using natBaCO3, and 81 ± 3 MBq of 133La and 48 ± 1 MBq of 135La using natBa metal. At 11.9 MeV, 135La yields were 81 ± 2 MBq, 6.8 ± 0.4 MBq, and 9.9 ± 0.5 MBq for 135BaCO3, natBaCO3, and natBa metal. BaCO3 target material recovery was 95.4% ± 1.7%. National Electrical Manufacturers Association and Derenzo phantom imaging demonstrated that 133La PET spatial resolution and scanner recovery coefficients were superior to those of 68Ga and 132La and comparable to those of 89Zr. The apparent molar activity was 130 ± 15 GBq/µmol with DOTA, 73 ± 18 GBq/µmol with PSMA-I&T, and 206 ± 31 GBq/µmol with macropa. Preclinical PET imaging with 133La-PSMA-I&T provided high-resolution tumor visualization with an SUV of 0.97 ± 0.17 at 60 min. Conclusion: With high-yield 133La cyclotron production, recovery of BaCO3 target material, and fundamental imaging characteristics superior to those of 68Ga and 132La, 133La represents a promising radiometal candidate to provide high-resolution PET imaging as a PET/α-therapy theranostic pair with 225Ac or as a PET/Auger electron therapy theranostic pair with 135La.
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Affiliation(s)
- Bryce J B Nelson
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
| | - Simon Ferguson
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
| | - Melinda Wuest
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
- Cancer Research Institute of Northern Alberta, University of Alberta, Edmonton, Alberta, Canada; and
| | - John Wilson
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
| | - M John M Duke
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
| | - Susan Richter
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
- Cancer Research Institute of Northern Alberta, University of Alberta, Edmonton, Alberta, Canada; and
| | - Hans Soenke-Jans
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
- Cancer Research Institute of Northern Alberta, University of Alberta, Edmonton, Alberta, Canada; and
| | - Jan D Andersson
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
- Edmonton Radiopharmaceutical Center, Cross Cancer Institute, Alberta Health Services, Edmonton, Alberta, Canada
| | - Freimut Juengling
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada
| | - Frank Wuest
- Department of Oncology, Cross Cancer Institute, University of Alberta, Edmonton, Alberta, Canada;
- Cancer Research Institute of Northern Alberta, University of Alberta, Edmonton, Alberta, Canada; and
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Gray A, Davis A, Patelli E. Uncertainty Propagation in SINBAD Fusion Benchmarks with Total Monte Carlo and Imprecise Probabilities. Fusion Science and Technology 2021. [DOI: 10.1080/15361055.2021.1895667] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- Ander Gray
- University of Liverpool, Institute for Risk and Uncertainty, Liverpool, United Kingdom
| | - Andrew Davis
- UKAEA, Culham Centre for Fusion Energy, Oxfordshire, United Kingdom
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Kormazeva ES, Khomenko IA, Unezhev VN, Aliev RA. Experimental study of α-particle induced reactions on natural erbium for the production of Auger-emitters 167Tm, 165Er and 169Yb. Appl Radiat Isot 2021; 177:109919. [PMID: 34509002 DOI: 10.1016/j.apradiso.2021.109919] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 04/21/2021] [Revised: 07/22/2021] [Accepted: 08/23/2021] [Indexed: 11/27/2022]
Abstract
The cross sections for nuclear reactions natEr(α,x) were measured in the energy range 60 → 10 MeV using the stacked-foil technique. The experiments were carried out in a wider energy range in comparison with previous works. The results are consistent with other studies and modeling using TENDL-2019. The 167Tm yield was 5.4 MBq/μAh in the range 60 → 30 MeV, and the main long-lived impurity is 168Tm (0.78% in terms of activity). The 165Tm yield is 4.6 MBq/μAh (60 → 40 MeV). 169Yb is formed with a yield of 1.0 MBq/μAh in the energy range 60 → 20 MeV.
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Affiliation(s)
- E S Kormazeva
- National Research Center «Kurchatov Institute», 1, Akademika Kurchatova pl., Moscow, 123182, Russian Federation.
| | - I A Khomenko
- National Research Center «Kurchatov Institute», 1, Akademika Kurchatova pl., Moscow, 123182, Russian Federation
| | - V N Unezhev
- National Research Center «Kurchatov Institute», 1, Akademika Kurchatova pl., Moscow, 123182, Russian Federation
| | - R A Aliev
- National Research Center «Kurchatov Institute», 1, Akademika Kurchatova pl., Moscow, 123182, Russian Federation
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Kos B, Čufar A, Kodeli IA. ASUSD nuclear data sensitivity and uncertainty program package: Validation on fusion and fission benchmark experiments. Nuclear Engineering and Technology 2021. [DOI: 10.1016/j.net.2021.01.034] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Bholane GT, Ganesapandy TS, Phatangare AB, Bharud VD, Patil BJ, Dahiwale SS, Suryanarayana SV, Bhoraskar VN, Dhole SD. The flux weighted cross sections of 179Hf(γ,γ') 179mHf and natHf(γ,x) 179mHf reactions at 8 MeV and 15 MeV bremsstrahlung end point energies. Appl Radiat Isot 2021; 174:109739. [PMID: 33930724 DOI: 10.1016/j.apradiso.2021.109739] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Key Words] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 10/14/2020] [Revised: 03/27/2021] [Accepted: 04/16/2021] [Indexed: 10/21/2022]
Abstract
For the hafnium element, the cross sections of 179Hf(γ,γ')179mHf and natHf(γ,x)179mHf reactions were measured at 8 MeV and 15 MeV bremsstrahlung end point energies respectively using activation method and off-line gamma-ray spectroscopy. The bremsstrahlung radiation spectra were generated by bombarding a 0.1 mm tungsten target with 8 MeV and 15 MeV electrons at 5 μA beam current and also theoretically simulated by GEANT4 computer code. The flux weighted average cross sections of 179Hf (γ,γ')179mHf and natHf(γ,x)179mHf reactions were measured by using 115In(γ,γ')115mIn and 197Au(γ,n)196Au as flux monitor reactions at 8 MeV and 15 MeV bremsstrahlung radiation respectively. The measured cross sections are found close to the corresponding theoretical cross sections estimated by TALYS 1.95 and TENDL 2019 computer codes. These hafnium cross sections at 8 MeV and 15 MeV bremsstrahlung radiation will be new additions to the EXFOR library, as so far not reported in literature.
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Affiliation(s)
- G T Bholane
- Microtron Accelerator Laboratory, Department of Physics, Savitribai Phule Pune University, Pune, 411007, India
| | - T S Ganesapandy
- Microtron Accelerator Laboratory, Department of Physics, Savitribai Phule Pune University, Pune, 411007, India
| | - A B Phatangare
- Microtron Accelerator Laboratory, Department of Physics, Savitribai Phule Pune University, Pune, 411007, India
| | - V D Bharud
- Microtron Accelerator Laboratory, Department of Physics, Savitribai Phule Pune University, Pune, 411007, India; Department of Physics, M. J. College, Jalgaon, 425002, India
| | - B J Patil
- Department of Physics, Abasaheb Garware College, Pune, 411004, India
| | - S S Dahiwale
- Microtron Accelerator Laboratory, Department of Physics, Savitribai Phule Pune University, Pune, 411007, India
| | - S V Suryanarayana
- Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai, 400085, India
| | - V N Bhoraskar
- Microtron Accelerator Laboratory, Department of Physics, Savitribai Phule Pune University, Pune, 411007, India.
| | - S D Dhole
- Microtron Accelerator Laboratory, Department of Physics, Savitribai Phule Pune University, Pune, 411007, India.
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Czakoj T, Košťál M, Losa E, Rypar V. NEW VALIDATION OF SI CROSS-SECTION USING SILICA SAND. EPJ Web Conf 2021. [DOI: 10.1051/epjconf/202124710001] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
Silicon cross-sections, being important for a criticality safety of final spent fuel disposals, were recently reevaluated within the IAEA INDEN project. Similarly, the thermal Scattering Law matrix for silicon dioxide, which is also important for criticality safety, was also reevaluated in the ENDF/B-VIII.0 library. Due to these reasons, a series of validation experiments with silica sand were performed at the LR-0 reactor. This paper describes these validation experiments, which used two different amounts of silica sand placed in the core. The first part of validation was carried out as critical experiments in order to benefit from the suitability of integral experiments for validation. The second part -fast neutron spectrum measurement in the sand -was performed in order to obtain knowledge of its characteristics and its agreement with a calculation. The results showed significant improvement of the Thermal Scattering Law matrix for silicon dioxide available in the ENDF/B-VIII.0 library. They also showed that the new INDEN evaluation of silicon cross-sections, together with its description in the ENDF/B-VIII.0 gives disagreement rate closest to the experiments carried out without silica sand insertions. The spectrum measurement showed that the calculations of fast neutron spectra in the sand show only slight differences between different evaluations of silicon cross-sections. However, the fast neutron spectrum is not dependent on the Thermal Scattering Law. The calculated spectra show relatively good agreement with the measurement.
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Abrate N, Dulla S, Ravetto P. UNCERTAINTY QUANTIFICATION IN FRENETIC CALCULATIONS OF ALFRED LEAD-COOLED FAST REACTOR. EPJ Web Conf 2021. [DOI: 10.1051/epjconf/202124715011] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
The paper shows the application of the most recent sensitivity techniques implemented in Serpent-2 in order to propagate the uncertainty from the nuclear data to the macroscopic, homogenised cross sections of the ALFRED reactor, which is then simulated with the multi-physics code FRENETIC. The main results are encouraging and define a possible methodology to propagate the nuclear data uncertainties to the main macroscopic parameters computed with FRENETIC, in order to perform thorough safety analyses for the ALFRED reactor.
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Alhassan E, Rochman D, Vasiliev A, Bergmann R, Wohlmuther M, Koning A, Ferroukhi H. In search of the best nuclear data file for proton induced reactions: Varying both models and their parameters. EPJ Web Conf 2020. [DOI: 10.1051/epjconf/202023913005] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
A lot of research work has been carried out in fine tuning model parameters to reproduce experimental data for neutron induced reactions. This however is not the case for proton induced reactions where large deviations still exist between model calculations and experiments for some cross sections. In this work, we present a method for searching both the model and model parameter space in order to identify the ’best’ nuclear reaction models with their parameter sets that reproduces carefully selected experimental data. Three sets of experimental data from EXFOR are used in this work: (1) cross sections of the target nucleus (2) cross sections of the residual nuclei and (3) angular distributions. Selected models and their parameters were varied simultaneously to produce a large set of random nuclear data files. The goodness of fit between our adjustments and experimental data was achieved by computing a global reduced chi square which took into consideration the above listed experimental data. The method has been applied for the adjustment of proton induced reactions on 59Co between 1 to 100 MeV. The adjusted files obtained are compared with available experimental data and evaluations from other nuclear data libraries.
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Saha U, Devan K. Assessment of neutron kerma coefficients and its calculation methodologies using recent basic ENDF-6 libraries. Nuclear Engineering and Design 2020; 360:110519. [DOI: 10.1016/j.nucengdes.2020.110519] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Abstract
The present article describes the preliminary validation study of simulated in-core and reflector n eutron spectra in preparation of oncoming experimental programs in the zeropower reactor CROCUS at EPFL. For this purpose, a set of activation foils were irradiated at three characteristic positions in the CROCUS reactor, and the subsequent activities were analyzed via γ spectrometry. The experimental setup was then modeled with the Monte Carlo neutron transport code Serpent2 and associated with an analysis tool to include the effect of the reactor power history during experiments.
The comparison of calculated and measured reaction rates (C/E) indicates a general consistency (at 2σ) between calculated and measured spectra. However, offsets of C/E values were observed in (n, γ) reactions, up to 18% for 115In and 8% for 63Cu dosimeters. This could be caused by an unexpected isotopic composition, uncertainties in nuclear data, or the spectrometry analysis.
In addition, a 100-groups spectrum unfolding was performed using the experimentally determined reaction rates and the Serpent2 spectra as the prior knowledge. The unfolded spectra were mainly adjusted in the thermal and fast ranges, while few modifications w ere m ade i n t he e pithermal r egion d ue t o the low contribution of epithermal neutrons in activation processes. Moreover, within energy groups where the capture reactions show resonant behavior, flux depletion (up to 38% as compared to the prior spectra) is observed due to the absence of self-shielding effect in the unfolding process. For this purpose, an unfolding method based on energy groups weighting is developed and tested.
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Laureau A, Lamirand V, Rochman D, Pautz A. Bayesian Monte Carlo assimilation for the PETALE experimental programme using inter-dosimeter correlation. EPJ Web Conf 2020. [DOI: 10.1051/epjconf/202023918004] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
This article presents the methodology developed to generate and use dosimeter covariances and to estimate nuisance parameters for the PETALE experimental programme. In anticipation of the final experimental results, this work investigates the consideration of these experimental correlations in the Bayesian assimilation process on nuclear data. Results show that the assimilation of a given set of dosimeters provides a strong constraint on some of the posterior reaction rate predictions of the other dosimeters. It confirms that, regarding the assimilation process, the different sets of dosimeters are correlated.
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Laureau A, Lamirand V, Rochman D, Pautz A. Uncertainty propagation based on correlated sampling technique for nuclear data applications. EPJ Nuclear Sci Technol 2020. [DOI: 10.1051/epjn/2020003] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files. The TMC-CS (Total Monte Carlo with Correlated Sampling) approach offers an interesting speed-up of the associated computation time. This methodology is detailed in this paper, together with two application cases to validate and illustrate the gain provided by this technique: the highly enriched uranium/iron metal core reflected by a stainless-steel reflector HMI-001 benchmark, and the PETALE experimental programme in the CROCUS zero-power light water reactor.
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Karkera M, Yerraguntla SS, Punchithaya S, Suryanarayana SV, Karantha MP, Naik H, Ganesan S, Dhanu LS, Kumar R, Deo K, Raj D, Patel T, Bishnoi S, Kannan U. Measurement and covariance analysis of $$ ^{232} {\text{Th}}\left( {{\text{n}},2{\text{n}}} \right)^{231} {\text{Th}} $$ reaction cross section. J Radioanal Nucl Chem 2019. [DOI: 10.1007/s10967-019-06722-3] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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Martín-fuertes, García, Fernández, Cortés, D’ovidio, Fernández, Pinna, Porfiri, Fischer, Ogando, Mota, Qiu, Helminen, Potempski, Gallego, Ibarra. Integration of Safety in IFMIF-DONES Design. Safety 2019; 5:74. [DOI: 10.3390/safety5040074] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022] Open
Abstract
The IFMIF-DONES (International Fusion Material Irradiation Facility-DEMO Oriented NEutron Source) facility is being designed with the general objective of providing irradiation of representative samples of power fusion machine materials under prototypical conditions. A linear accelerator will deliver deuterons at high intensity to circulating lithium in a loop, which will produce neutrons capable of obtaining the required damage conditions. As a result of this process, radionuclides will be produced as a by-product, which is characterized by several degrees of mobility. Shielding and radiation protection measures will be required in the facility. IFMIF-DONES will be classified as a first class radioactive facility according to national regulations, with Spain being the European candidate to site the facility. Several aspects of the main safety instructions affecting the facility’s design are explained and discussed in this paper.
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Fischer U, Bienkowska B, Drozdowicz K, Frisoni M, Mota F, Ogando F, Qiu Y, Stankunas G, Tracz G. Neutronics of the IFMIF-DONES irradiation facility. Fusion Engineering and Design 2019. [DOI: 10.1016/j.fusengdes.2019.02.057] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Kwon S, Konno C, Ohta M, Ochiai K, Sato S, Kasugai A. TENDL-2017 benchmark test with iron shielding experiment at QST/TIARA. Fusion Engineering and Design 2019; 144:209-214. [DOI: 10.1016/j.fusengdes.2019.05.009] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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