Nuclear data for production of the therapeutic radionuclides 32P, 64Cu 67Cu, 89Sr, 90Y and 153Sm via the (n,p) reaction:: Evaluation of excitation function and its validation via integral cross-section measurement using a 14MeV d(Be) neutron source
Nuclear data for production of the therapeutic radionuclides 32P, 64Cu 67Cu, 89Sr, 90Y and 153Sm via the (n,p) reaction:: Evaluation of excitation function and its validation via integral cross-section measurement using a 14MeV d(Be) neutron source
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DOI：
10.1016/j.apradiso.2005.12.020
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发表时间：
2006-06-01
影响因子：
1.6
通讯作者：
Coenen, HH
中科院分区：
文献类型：
--
作者：
Al-Abyad, M;Spahn, I;Coenen, HH
讨论了治疗用放射性核素(32)p、铜-、铜-67、锶-89、Y-90和Sm-153分别在靶核S-32、锌-、锌-67、Y-89、Zr-90和Eu-153上发生(n，p)反应产生的核数据。分析了关于每个激发函数的现有信息。根据推荐的每个反应的数据集，推导出了标准14 MeVd(Be)中子场的平均积分截面。实验上还测量了光谱平均截面。积分值与积分测量的比较用于在约15%的范围内验证激励函数。对于通过(n，p)过程以无载体形式生产上述放射性核素，快中子源似乎比裂变反应堆有效得多。特别讨论了生产高比活度(SM)--S-153的可能性。(C)2006爱思唯尔有限公司。保留所有权利。
Nuclear data for production of the therapeutic radionuclides (32)p, Cu-64, Cu-67, Sr-89, Y-90 and Sm-153 via (n,p) reactions on the target nuclei S-32, Zn-64, Zn-67, Y-89, Zr-90 and Eu-153, respectively, are discussed. The available information on each excitation function was analysed. From the recommended data set for each reaction the average integrated cross section for a standard 14 MeV d(Be) neutron field was deduced. The spectrum-averaged cross section was also measured experimentally. A comparison of the integrated value with the integral measurement served to validate the excitation function within about 15%. A fast neutron source appears to be much more effective than a fission reactor for production of the above-mentioned radionuclides in a no-carrier-added form via the (n,p) process. In particular, the possibility of production of high specific activity (SM)-S-153 is discussed. (c) 2006 Elsevier Ltd. All rights reserved.