RUPAC2018 - List of Authors (Savitskaya, E.N.)

Paper	Title	Page
WEPSB54	Selection of Materials for Target Station Equipment at Cyclotron Cyclon-70	391
	E.N. Savitskaya, M.A. Maslov, S.A. Nikitin, V.N. Peleshko, N.V. Skvorodnev IHEP, Moscow Region, Russia
	Funding: Work supported by the Ministry of Education and Science of the Russian Federation, the agreement ID 0000000007417-3I0002 A Radioisotope Centre of Nuclear Medicine for commercial production of radioisotopes is under construction now in Protvino. It is based on IBA (Belgium) Cyclone 70 proton cyclotron with proton energy up to 70 MeV and beam current up to 750 uA. The proton beam is split into two halves to provide simultaneous operation of two target stations. NRC KI - IHEP develops the design of the target station to produce nuclides Sr82 and Ge68 by the 70 MeV proton beam with current up to 375uA (2.3x10¹⁵ proton/s). The present work is devoted to selection of target station materials to minimize the induced radioactivity of equipment during isotopes production. The main source of this radioactivity is a flux of secondary neutrons cre-ated from proton-nuclear interactions with target materials. The nucleon-nucleus interactions and the transport of particles in substances were simulated by package of Monte Carlo codes HADR99 and FAN15 specially adapted for this task. Time dependence of the activity of nuclides accumulated in surrounding equipment and the effective dose rate after the end of bombardment (EOB) were calculated. Several alloys were considered and aluminum alloy AMg2 was chosen as most promising base material.
DOI •	reference for this paper ※ https://doi.org/10.18429/JACoW-RUPAC2018-WEPSB54
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WEPSB55	On the Formation of Induced Radioactivity on the U-70 Proton Accelerator
	Ja.N. Rascvetalov, G.I. Britvich, G.I. Krupny, M.A. Maslov, V.N. Peleshko, E.N. Savitskaya IHEP, Moscow Region, Russia
	Global induced radioactivity levels on the main ring of proton 70 GeV accelerator (U-70) were estimated. Modeling results of induced radioactivity accumulation on the typical particle canal downstream internal target by Monte Carlo method are given. The wide set of various material specimens was espoused during one U-70 run in vicinity of internal target and specific radioactivity of identified long-lived nuclides was measured. Decay curves of ambient dose and specific radioactivity were calculated and analyzed for all activated specimens. Some fragments of U-70 equipment from radioactive waste storage also were investigated and specific radioactivity of their long-lived nuclides were measured. Unexpectedly 44Ti with 60 years half-life was identified in some cooper and stainless steel fragments. Production cross sections of 44Ti (and other nuclides) on copper were evaluated after irradiation by 50 GeV protons. These data can be used to provide radiation safety when working with radioactive elements of accelerator equipment, as well as storing and disposing of radioactive waste.
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Paper

Title

Page

Selection of Materials for Target Station Equipment at Cyclotron Cyclon-70

391

E.N. Savitskaya, M.A. Maslov, S.A. Nikitin, V.N. Peleshko, N.V. Skvorodnev
IHEP, Moscow Region, Russia

Funding: Work supported by the Ministry of Education and Science of the Russian Federation, the agreement ID 0000000007417-3I0002
A Radioisotope Centre of Nuclear Medicine for commercial production of radioisotopes is under construction now in Protvino. It is based on IBA (Belgium) Cyclone 70 proton cyclotron with proton energy up to 70 MeV and beam current up to 750 uA. The proton beam is split into two halves to provide simultaneous operation of two target stations. NRC KI - IHEP develops the design of the target station to produce nuclides Sr82 and Ge68 by the 70 MeV proton beam with current up to 375uA (2.3x10¹⁵ proton/s). The present work is devoted to selection of target station materials to minimize the induced radioactivity of equipment during isotopes production. The main source of this radioactivity is a flux of secondary neutrons cre-ated from proton-nuclear interactions with target materials. The nucleon-nucleus interactions and the transport of particles in substances were simulated by package of Monte Carlo codes HADR99 and FAN15 specially adapted for this task. Time dependence of the activity of nuclides accumulated in surrounding equipment and the effective dose rate after the end of bombardment (EOB) were calculated. Several alloys were considered and aluminum alloy AMg2 was chosen as most promising base material.

DOI •

reference for this paper ※ https://doi.org/10.18429/JACoW-RUPAC2018-WEPSB54

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reference for this paper using ※ BibTeX, ※ LaTeX, ※ Text/Word, ※ RIS, ※ EndNote (xml)

WEPSB55

On the Formation of Induced Radioactivity on the U-70 Proton Accelerator

Ja.N. Rascvetalov, G.I. Britvich, G.I. Krupny, M.A. Maslov, V.N. Peleshko, E.N. Savitskaya
IHEP, Moscow Region, Russia

Global induced radioactivity levels on the main ring of proton 70 GeV accelerator (U-70) were estimated. Modeling results of induced radioactivity accumulation on the typical particle canal downstream internal target by Monte Carlo method are given. The wide set of various material specimens was espoused during one U-70 run in vicinity of internal target and specific radioactivity of identified long-lived nuclides was measured. Decay curves of ambient dose and specific radioactivity were calculated and analyzed for all activated specimens. Some fragments of U-70 equipment from radioactive waste storage also were investigated and specific radioactivity of their long-lived nuclides were measured. Unexpectedly 44Ti with 60 years half-life was identified in some cooper and stainless steel fragments. Production cross sections of 44Ti (and other nuclides) on copper were evaluated after irradiation by 50 GeV protons. These data can be used to provide radiation safety when working with radioactive elements of accelerator equipment, as well as storing and disposing of radioactive waste.

Export •

reference for this paper using ※ BibTeX, ※ LaTeX, ※ Text/Word, ※ RIS, ※ EndNote (xml)