Results 11 to 20 of about 2,888 (188)

A simulational study of the indirect-geometry neutron spectrometer BIFROST at the European Spallation Source, from neutron source position to detector position. [PDF]

J Appl Crystallogr, 2021
The incident detector rates that are anticipated for the indirect‐geometry cold‐neutron spectrometer BIFROST at the European Spallation Source are estimated, and the use of powerful simulation tools for the correct interpretation of neutron transport in crystalline materials is demonstrated.The European Spallation Source (ESS) is intended to become the
Klausz M, Kanaki K, Kittelmann T, Toft-Petersen R, Birk JO, Olsen MA, Zagyvai P, Hall-Wilton RJ.   +7 more
europepmc   +2 more sources

A feasibility study of the therapeutic application of a mixture of ^67/64 Cu radioisotopes produced by cyclotrons with proton irradiation. [PDF]

Med Phys, 2022
Abstract Purpose 64Cu and 67Cu radioisotopes have nuclear characteristics suitable for nuclear medicine applications. The production of 64Cu is already well established. However, the production of 67Cu in quantities suitable to conduct clinical trials is more challenging as it leads to the coproduction of other Cu isotopes, in particular 64Cu.
De Nardo L, Pupillo G, Mou L, Esposito J, Rosato A, Meléndez-Alafort L.   +5 more
europepmc   +2 more sources

Results of a Geant4 benchmarking study for bio-medical applications, performed with the G4-Med system. [PDF]

Med Phys
Abstract Background Geant4, a Monte Carlo Simulation Toolkit extensively used in bio‐medical physics, is in continuous evolution to include newest research findings to improve its accuracy and to respond to the evolving needs of a very diverse user community.
Arce P, Archer JW, Arsini L, Bagulya A, Bolst D, Brown JMC, Caccia B, Chacon A, Cirrone GAP, Cortés-Giraldo MA, Cutajar D, Cuttone G, Dondero P, Dotti A, Faddegon B, Fattori S, Fedon C, Guatelli S, Haga A, Incerti S, Ivanchenko V, Konstantinov D, Kyriakou I, Le A, Li Z, Maire M, Malaroda A, Mancini-Terracciano C, Mantero A, Michelet C, Milluzzo G, Nicolanti F, Novak M, Omachi C, Pandola L, Pensavalle JH, Perales Á, Perrot Y, Petringa G, Pozzi S, Quesada JM, Ramos-Méndez J, Romano F, Rosenfeld AB, Safavi-Naeini M, Sakata D, Sarmiento LG, Sasaki T, Sato Y, Sciuto A, Sechopoulos I, Simpson EC, Stanzani R, Tomal A, Toshito T, Tran HN, White C, Wright DH.   +57 more
europepmc   +2 more sources

Present Status of Neutron-, Photo-induced and Spontaneous Fission Yields Experimental Data [PDF]

EPJ Web of Conferences, 2020
Nuclear reaction data collection, evaluation and dissemination have been pioneered at the Brookhaven National Laboratory since the early 50s. These activities gained popularity worldwide, and around 1970 the experimental nuclear reaction data interchange
Pritychenko B., Schwerer O., Totans J., Gritzay O.   +3 more
doaj   +1 more source

Completeness Check of Experimental Fission Product Yield Data in EXFOR Database [PDF]

EPJ Web of Conferences, 2020
The IAEA conducted the completeness assessment of fission product yield (FPY) data in EXFOR database against two bibliographies that were used in ENDF/B-VI and UKFY3.0 library evaluations. We found that 194 articles are found to be relevant for new entry.
Okumura Shin
doaj   +1 more source

The innovative 52gMn for positron emission tomography (PET) imaging: Production cross section modeling and dosimetric evaluation

Medical Physics, Volume 50, Issue 3, Page 1843-1854, March 2023., 2023
Abstract Background Manganese is a paramagnetic element suitable for magnetic resonance imaging (MRI) of neuronal function. However, high concentrations of Mn2 + can be neurotoxic. 52gMn may be a valid alternative as positron emission tomography (PET) imaging agent, to obtain information similar to that delivered by MRI but using trace levels of Mn2 + ,
Francesca Barbaro, Luciano Canton, Mario Pietro Carante, Alessandro Colombi, Laura De Nardo, Andrea Fontana, Laura Meléndez‐Alafort   +6 more
wiley   +1 more source

Towards the high-accuracy determination of the 238U fission cross section at the threshold region at CERN - N-TOF [PDF]

, 2015
The 238U fission cross section is an international standard beyond 2 MeV where the fission plateau starts. However, due to its importance in fission reactors, this cross-section should be very accurately known also in the threshold region below 2 MeV ...
A. Couture, A. Ferrari, A. Goverdovski, A. Manousos, A. Mengoni, A. Musumarra, A. Pavlik, A. Plompen, A. Poch, A. Riego, A. Saxena, A. Tsinganis, A. Ventura, A. Wallner, A.R. Garcia, B. Berthier, Barbagallo, Birgesson, C. Carrapiço, C. Domingo-Pardo, C. Eleftheriadis, C. Guerrero, C. Lampoudis, C. Langer, C. Le Naour, C. Lederer, C. Massimi, C. Moreau, C. Paradela, C. Pretel, C. Rubbia, C. Santos, C. Stephan, C. Weiß, Calviani, Calviani, Carlson, Colonna, D. Bosnar, D. Cano-Ott, D. Karadimos, D. Karamanis, D. Schumann, D. Tarrio, D. Villamarin, D.G. Jenkins, E. Berthoumieux, E. Chiaveri, E. Dupont, E. Gonzalez-Romero, E. Griesmayer, E. Jericha, E. Leal-Cidoncha, E. Mendoza, F. Alvarez-Velarde, F. Becvar, F. Belloni, F. Calvino, F. Cerutti, F. Gramegna, F. Gunsing, F. Kaeppeler, F. Mingrone, F. Roman, F. Voss, G. Aerts, G. Badurek, G. Cortes, G. Giubrone, G. Rudolf, G. Tagliente, G. Vannini, Guerrero, H. Alvarez, H. Leeb, I. Dillmann, I. Duran, I.F. Goncalves, J. Andrzejewski, J. Billowes, J. Cox, J. Kroll, J. Marganiec, J. Pancin, J. Perkowski, J. Praena, J. Quesada, J. Salgado, J.L. Tain, K. Fraval, K. Fujii, K. Wisshak, Karadimos, Karadimos, L. Audouin, L. Cosentino, L. Ferrant, L. Perrot, L. Plukis, L. Sarchiapone, L. Tassan-Got, L. Tavora, L.S. Leong, M. Barbagallo, M. Brugger, M. Calviani, M. Chin, M. Diakaki, M. Embid-Segura, M. Heil, M. Igashira, M. Kerveno, M. Kokkoris, M. Krticka, M. Lozano, M. Mastromarco, M. Mirea, M. Mosconi, M. Weigand, M. Wiesher, M.A. Cortes-Giraldo, M.B. Gomez-Hornillos, M.C. Vincente, M.J. Vermeulen, M.T. Pigni, N. Colonna, N. Kivel, N. Patronis, O. Serot, Otuka, P. Baumann, P. Cennini, P. Finocchiaro, P. Gurusamy, P. Mastinu, P. Pavlopoulos, P. Rullhusen, P. Schillebeeckx, P. Vaz, P. Zugec, P.M. Milazzo, Paradela, Paradela, R. Capote, R. Dressler, R. Haight, R. Losito, R. Plag, R. Reifarth, R. Sarmento, R. Terlizzi, R. Versaci, R. Vlastou, S. Altstadt, S. Andriamonje, S. David, S. Ganesan, S. Heinitz, S. Isaev, S. Lo Meo, S. Marrone, S. O’Brien, S. Schmidt, S. Valenta, S. Walter, T. Martinez, T. Rauscher, T. Ware, T. Wright, Tarrio, Tarrio, Tarrio, V. Becares, V. Boccone, V. Ketlerov, V. Konovalov, V. Variale, V. Vlachoudis, W. Dridi, W. Furman, W. Mondelaers, Weiss, Y. Kadi   +182 more
core   +20 more sources

131Cs Radyoizotopunun Üretildiği Bazı Nükleer Reaksiyonların Uyarılma Fonksiyonları

Süleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi Fen Dergisi, 2020
Nükleer fizikteki sürekli devam eden gelişmeler nükleer teknolojiye önemli katkılar sağlamakta ve bağlantılı olan birçok alanda da önemli gelişmeler olmasını sağlamaktadır.
İsmail Hakkı Sarpün, Sedat Zengin, Vildan Özkan Bilici   +2 more
doaj   +1 more source

Measurement of neutron-induced fission cross sections of 232Th from 1 to 300 MeV at CSNS Back-n

Physics Letters B, 2023
232Th/233U fuel cycle is an alternate candidate for future nuclear energy. Neutron-induced fission cross section of 232Th is one of the important nuclear data if using thorium as the fuel in the future.
Yonghao Chen, Yiwei Yang, Zhizhou Ren, Wei Jiang, Ruirui Fan, Han Yi, Rong Liu, Jingyu Tang, Hantao Jing, Yang Li, Qiang Li, Zhixin Tan, Qi An, Jiangbo Bai, Jie Bao, Yu Bao, Ping Cao, Haolei Chen, Qiping Chen, Zhen Chen, Zengqi Cui, Changqing Feng, Keqing Gao, Xiaolong Gao, Minhao Gu, Changcai Han, Zijie Han, Guozhu He, Yongcheng He, Yang Hong, Yiwei Hu, Hanxiong Huang, Xiru Huang, Haoyu Jiang, Zhijie Jiang, Ling Kang, Bo Li, Chao Li, Jiawen Li, Xiao Li, Jie Liu, Shubin Liu, Xingyan Liu, Ze Long, Guangyuan Luan, Changjun Ning, Mengchen Niu, Binbin Qi, Jie Ren, Xichao Ruan, Zhaohui Song, Kang Sun, Zhijia Sun, Xinyi Tang, Binbin Tian, Lijiao Wang, Pengcheng Wang, Zhaohui Wang, Zhongwei Wen, Xiaoguang Wu, Xuan Wu, Likun Xie, Xiaoyun Yang, Li Yu, Tao Yu, Yongji Yu, Guohui Zhang, Linhao Zhang, Qiwei Zhang, Xianpeng Zhang, Yuliang Zhang, Zhiyong Zhang, Luping Zhou, Zhihao Zhou, Kejun Zhu   +74 more
doaj   +1 more source

Solution of neutron-transport multigroup equations system in subcritical systems [PDF]

Nuclear Energy and Technology, 2018
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffusion approximation. A thermoelectric generator containing plutonium dioxide, used as a source of thermal and electric power in spacecraft, was studied.
Igor V. Shamanin, Sergey V. Bedenko, Vladimir N. Nesterov, Igor O. Lutsik, Anatoly A. Prets   +4 more
doaj   +3 more sources