MONTE-CARLO SIMULATIONS OF NEUTRON-TRANSPORT IN A LINAC RADIOTHERAPY ROOM

被引：5

作者：

AGOSTEO, S

PARA, AF

SILARI, M

TORRESIN, A

TOSI, G

机构：

[1] POLITECN MILAN,DIPARTIMENTO INGN NUCL,VIA PONZIO 34-3,I-20133 MILAN,ITALY

[2] CNR,IST TECNOL BIOMED AVANZATE,I-20131 NILANO,ITALY

[3] OSPED NIGUARDA MILANO,SERV FIS SANITARIA,I-20162 MILAN,ITALY

来源：

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS | 1992年 / 72卷 / 01期

关键词：

D O I：

10.1016/0168-583X(92)95287-2

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

Medical electron accelerators for cancer radiation therapy operating at energies above 8-10 MeV produce secondary neutron radiation via (gamma, n) and (e, e'n) reactions in the various materials of the gantry. The spatial distribution of the neutron flux in the treatment room can be evaluated by the Monte Carlo method. The influence of the materials constituting the bremsstrahlung target and the gantry shield on the angular and the spatial distributions of the direct component of the flux has been evaluated by the MCNP code. The effect of room geometry and composition of wall materials on the scattered component has also been investigated.

引用

页码：84 / 90

页数：7

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