Preliminary studies for the PDX tokamak radiation shield design
Shielding calculations have been done to arrive at a preliminary radiation shield design for the Poloidal Diverter Experiment (PDX) tokamak at PPPL. The PDX, which will be used to study plasma impurities in tokamaks, may generate up to 10/sup 18/ 2.5-MeV neutrons per year from D--D reactions and 5 x 10/sup 15/ 14-MeV neutrons per year from D--T reactions. It was determined that shielding doors and a shielding roof must be added to the existing .813-m (32-in.) heavy (i.e., high density) concrete walls to reduce radiation doses to the control room adjacent to PDX and to the site boundary 150 m away to acceptable levels. A .381-m (15-in.) thick roof composed of borated water (5000 ppM) contained in steel cans was recommended. Two doors leading to the control room should be .305 m (1 ft) of polyethylene or water-filled cans backed by 5.08 cm (2 in.) of steel or lead.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6208673
- Report Number(s):
- TREE-1369; TRN: 79-016806
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PDX DEVICES
SHIELDING
NEUTRON TRANSPORT THEORY
BORON
COMPUTER CALCULATIONS
CONCRETES
NEUTRON FLUX
POLYETHYLENES
WATER
BUILDING MATERIALS
DIVERTORS
ELEMENTS
HYDROGEN COMPOUNDS
MATERIALS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
POLYMERS
POLYOLEFINS
RADIATION FLUX
SEMIMETALS
TRANSPORT THEORY
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