Shielding measurements for 230-Mev protons
- Univ. of Wisconsin, Madison (United States). Dept. of Medical Physics
- Loma Linda Univ., CA (United States). Medical Center
Energetic neutrons, produced as protons interact with matter, dominate the radiation shielding environment for proton accelerators. Because of the scarcity of data describing the shielding required to protect personnel from these neutrons, absorbed dose and dose-equivalent values are measured as a function of depth in a thick concrete shield at neutron emission angles of 0, 22, 45, and 90 deg for 230-MeV protons incident upon stopping-length aluminum, iron, and lead targets. Neutron attenuation lengths vary sharply with angle but are independent of the target material. Comparing results with prior shielding calculations, the High-Energy Transport Code overestimates neutron production and attenuation lengths in the forward direction. Analytical methods compare favorably in the forward direction but overestimate the production and attenuation lengths at large angles. The results presented are useful for determining the shielding requirements for proton radiotherapy facilities and as a benchmark for future calculations.
- OSTI ID:
- 6109285
- Journal Information:
- Nuclear Science and Engineering; (United States), Vol. 115:1; ISSN 0029-5639
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
43 PARTICLE ACCELERATORS
ACCELERATORS
BIOLOGICAL SHIELDS
CONCRETES
NEUTRON TRANSPORT
NEUTRONS
ABSORPTION
ALUMINIUM
IRON
LEAD
PROTON REACTIONS
PROTONS
RADIOTHERAPY
SHIELDING MATERIALS
BARYON REACTIONS
BARYONS
BUILDING MATERIALS
CHARGED-PARTICLE REACTIONS
ELEMENTARY PARTICLES
ELEMENTS
FERMIONS
HADRON REACTIONS
HADRONS
MATERIALS
MEDICINE
METALS
NEUTRAL-PARTICLE TRANSPORT
NUCLEAR MEDICINE
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
RADIATION TRANSPORT
RADIOLOGY
SHIELDS
SORPTION
THERAPY
TRANSITION ELEMENTS
663610* - Neutron Physics- (1992-)
430100 - Particle Accelerators- Design
Development
& Operation