Application and Validation of Particle Transport Code PHITS in Design of J-PARC 1 MW Spallation Neutron Source
Application and Validation of Particle Transport Code PHITS in Design of J-PARC 1 MW Spallation Neutron Source
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粒子输运代码PHITS在J-PARC 1 MW散裂中子源设计中的应用与验证
DOI：
10.15669/pnst.2.872
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发表时间：
2011
期刊：
影响因子：
--
通讯作者：
Masatoshi Futak
中科院分区：
文献类型：
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作者：
M. Harada;F. Maekawa;K. Oikawa;S. Meigo;H. Takada;Masatoshi Futak
日本质子加速器中子源（JSNS）是日本质子加速器研究综合体（J-PARC）的主要实验设施之一。JSNS使用3 GeV和1 MW脉冲质子束运行，具有世界上最高的中子强度。在设计阶段，以最佳中子学性能为目标，充分应用PHITS程序进行JSNS中子学设计，并使用复杂的模型进行了数千例计算。利用PHITS程序不仅进行了中子性能优化，还进行了屏蔽计算、工程设计中的核热估算、容器设计中的剩余放射性估算以及寿命和维护设计中的辐射损伤估算。JSNS是世界上第一个完全采用这种模拟代码进行中子学设计的设施之一。在这些计算中，注意粒子能量从GeV到meV（12个十年）的变化，中子通量减少了10个十年或更多。为了证实其可靠性，这些计算进行了验证的测量数据的中子谱强度，脉冲形状，核发热，和放射性。结果表明，计算值与实测值吻合较好。我们证实，PHITS代码是可靠的，这样的设计计算。同时，这也表明PHITS程序是其它辐射源设施和加速器设施中子学设计的有力工具。
The Japan Spallation Neutron Source (JSNS) is one of the major experimental facilities in the Japan Proton Accelerator Research Complex (J-PARC). JSNS operates with 3 GeV and 1 MW pulsed proton beams, and has the highest-class neutron intensity in the world. In the design stage, aiming for the best neutronic performance, the PHITS code was fully applied in the JSNS neutronics design, and calculations for several thousand cases were performed using complicated models. Not only optimization of neutronic performance, but also shielding calculation, nuclear heat estimation for the engineering design, residual radioactivity estimation for the cask design, and radiation damage estimation for the life and maintenance design were also done with the PHITS code. JSNS is one of the first facilities in the world to fully adapt such a simulation code to the neutronics design. In these calculations, note the change in particle energy from GeV to meV (12 decades), and that neutron fluxes are reduced by 10 decades or more. To confirm their reliability, these calculations were validated by measurement data for neutron spectral intensities, pulse shape, nuclear heat generation, and radioactivity. The results showed that the calculated values were in good agreement with the measured values. We confirmed that the PHITS code was reliable for such design calculations. At the same time, this indicates that the PHITS code is a powerful tool for neutronic design in other radiation source facilities and accelerator facilities.