ITER Generic Diagnostic Upper Port Plug Nuclear Heating and Personnel Dose Rate Assessment
Description
Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support of the integration of diagnostics in to the ITER Upper Port Plugs. Simplified shielding models of the Visible-Infrared diagnostic and of a large aperture diagnostic were incorporated in to the ITER global CAD model. Results for these systems are representative of typical designs with maximum shielding and a small aperture (Vis-IR) and minimal shielding with a large aperture. The neutronics discrete-ordinates code ATTILA(regsign) and SEVERIAN(regsign) (the ATTILA parallel processing version) was used. Material properties and the 500 MW D-T volume source were taken from the ITER 'Brand Model' MCNP benchmark model. A biased quadrature set equivalent to Sn=32 and a scattering degree of Pn=3 were used along with a 46-neutron and 21-gamma FENDL energy subgrouping. Total nuclear heating (neutron plug gamma heating) in the upper port plugs ranged between 380 and 350 kW for the Vis-IR and Large Aperture cases. The Large Aperture model exhibited lower total heating but much higher peak volumetric heating on the upper port plug structure. Personnel dose rates are calculated in a three step process involving a neutron-only transport calculation, the generation of activation volume sources at pre-defined time steps and finally gamma transport analyses are run for selected time steps. ANSI-ANS 6.1.1 1977 Flux-to-Dose conversion factors were used. Dose rates were evaluated for 1 full year of 500 MW DT operation which is comprised of 3000 1800-second pulses. After one year the machine is shut down for maintenance and personnel are permitted to access the diagnostic interspace after 2-weeks if dose rates are below 100 (micro)Sv/hr. Dose rates in the Visible-IR diagnostic model after one day of shutdown were 130 (micro)Sv/hr but fell below the limit to 90 (micro)Sv/hr 2-weeks later. The Large Aperture style shielding model exhibited higher and more persistent dose rates. After 1-day the dose rate was 230 (micro)Sv/hr but was still at 120 (micro)Sv/hr 4-weeks later.
Availability note (English)
Also available from OSTI as DE00964190; PURL: https://www.osti.gov/servlets/purl/964190-ynrvLH/
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- PPPL--4451
Conference
- Title
- 36. International Conference on Plasma Science (ICOPS); 23. Symposium on Fusion Engineering (SOFE)
- Dates
- 31 May - 5 Jun 2009
- Place
- San Diego, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 41011895
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- APERTURES; BENCHMARKS; DISCRETE ORDINATE METHOD; DOSE RATES; HEATING RATE; ITER TOKAMAK; MAINTENANCE; PARALLEL PROCESSING; PERSONNEL; RADIATION HEATING; SCATTERING; SHIELDING; SHUTDOWN
- Descriptors DEC
- CALCULATION METHODS; CLOSED PLASMA DEVICES; HEATING; OPENINGS; PROGRAMMING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Contract/Grant/Project number
- ACO2-09CH11466
- Notes
- doi 10.2172/953485
- Funding organization
- USDOE Office of Science (United States)