Accelerator shield design of KIPT neutron source facility
Creators
- 1. Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States)
Description
Argonne National Laboratory (ANL) of the United States and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have been collaborating on the design development of a neutron source facility at KIPT utilizing an electron-accelerator-driven subcritical assembly. Electron beam power is 100 kW, using 100 MeV electrons. The facility is designed to perform basic and applied nuclear research, produce medical isotopes, and train young nuclear specialists. The biological shield of the accelerator building is designed to reduce the biological dose to less than 0.5-mrem/hr during operation. The main source of the biological dose is the photons and the neutrons generated by interactions of leaked electrons from the electron gun and accelerator sections with the surrounding concrete and accelerator materials. The Monte Carlo code MCNPX serves as the calculation tool for the shield design, due to its capability to transport electrons, photons, and neutrons coupled problems. The direct photon dose can be tallied by MCNPX calculation, starting with the leaked electrons. However, it is difficult to accurately tally the neutron dose directly from the leaked electrons. The neutron yield per electron from the interactions with the surrounding components is less than 0.01 neutron per electron. This causes difficulties for Monte Carlo analyses and consumes tremendous computation time for tallying with acceptable statistics the neutron dose outside the shield boundary. To avoid these difficulties, the SOURCE and TALLYX user subroutines of MCNPX were developed for the study. The generated neutrons are banked, together with all related parameters, for a subsequent MCNPX calculation to obtain the neutron and secondary photon doses. The weight windows variance reduction technique is utilized for both neutron and photon dose calculations. Two shielding materials, i.e., heavy concrete and ordinary concrete, were considered for the shield design. The main goal is to maintain the total dose outside the shield boundary at less than 0.5-mrem/hr. The shield configuration and parameters of the accelerator building have been determined and are presented in this paper. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-700-2
- Imprint Title
- Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
- Imprint Pagination
- 3016 p.
- Journal Page Range
- p. 524-534
Conference
- Title
- 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
- Acronym
- M and C 2013
- Dates
- 5-9 May 2013
- Place
- Sun Valley, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 45033692
- Subject category
- S43: PARTICLE ACCELERATORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATORS; BIOLOGICAL SHIELDS; COMPUTERIZED SIMULATION; CONCRETES; DESIGN; ELECTRON BEAMS; ELECTRON GUNS; ELECTRONS; MONTE CARLO METHOD; NEUTRON SOURCE FACILITIES; NEUTRON SOURCES; NEUTRONS; PHOTONS; RADIATION DOSES; SHIELDING MATERIALS
- Descriptors DEC
- BARYONS; BEAMS; BOSONS; BUILDING MATERIALS; CALCULATION METHODS; DOSES; ELEMENTARY PARTICLES; FERMIONS; HADRONS; LEPTON BEAMS; LEPTONS; MASSLESS PARTICLES; MATERIALS; NUCLEONS; PARTICLE BEAMS; PARTICLE SOURCES; RADIATION SOURCES; SHIELDS; SIMULATION
Optional Information
- Notes
- 9 refs.