Shielding calculations for the TFTR neutral beam injectors
Two-dimensional discrete ordinates calculations have been performed to determine the location and thickness of concrete shielding around the Tokamak Fusion Test Reactor (TFTR) neutral beam injectors. Two sets of calculations were performed: one to determine the dose equivalent rate on the roof and walls of the test cell building when no injectors are present, and one to determine the contribution to the dose equivalent rate at these locations from radiation streaming through the injection duct. Shielding the side and rear of the neutral beam injector with 0.305 and 0.61 m of concrete, respectively, and lining the inside of the test cell wall with an additional layer of concrete having a thickness of 0.305 m and a height above the axis of deuteron injection of 3.10 m are sufficient to maintain the biological dose equivalent rate outside the test cell to approx. 1 mrem/DT pulse.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6123364
- Report Number(s):
- ORNL/TM-6949
- Country of Publication:
- United States
- Language:
- English
Similar Records
Shielding calculations for the Tokamak Fusion Test Reactor neutral beam injectors
Design of the precast, post-tensioned concrete shielding structure for the TFTR neutral beam test cell
Dose rates from induced activity in the TFTR test cell
Journal Article
·
Fri Feb 29 23:00:00 EST 1980
· Nucl. Technol.; (United States)
·
OSTI ID:5281248
Design of the precast, post-tensioned concrete shielding structure for the TFTR neutral beam test cell
Conference
·
Wed Dec 31 23:00:00 EST 1980
· Proc. Symp. Eng. Probl. Fusion Res.; (United States)
·
OSTI ID:6361506
Dose rates from induced activity in the TFTR test cell
Technical Report
·
Wed Aug 01 00:00:00 EDT 1979
·
OSTI ID:6130681
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
BUILDING MATERIALS
CONCRETES
DISCRETE ORDINATE METHOD
MATERIALS
NEUTRAL BEAM SOURCES
SHIELDING
TFTR REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TWO-DIMENSIONAL CALCULATIONS
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
BUILDING MATERIALS
CONCRETES
DISCRETE ORDINATE METHOD
MATERIALS
NEUTRAL BEAM SOURCES
SHIELDING
TFTR REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TWO-DIMENSIONAL CALCULATIONS