Radiation analysis of the CIT (Compact Ignition Tokamak) pellet injector system and its impact on personnel access

Technical Report · Mon Aug 01 04:00:00 EDT 1988

DOI:https://doi.org/10.2172/6758543· OSTI ID:6758543

Selcow, E C; Stevens, P N; Gomes, I C; Gomes, L M

The conceptual design of the Compact Ignition Tokamak (CIT) is nearing completion. The CIT is a short-pulse ignition experiment, which is planned to follow the operations of the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory (PPPL). The high neutron wall loadings, 4--5 MW/m/sup 2/, associated with the operation of this device require that neutronics-related issues be considered in the overall system design. Radiation shielding is required for the protection of device components as well as personnel. A close-in igloo shield has been designed around the periphery of the tokamak structure, and the entire experiment is housed in a circular test cell facility that has a radius of 12 m. The most critical radiation concerns in the CIT design process relate to the numerous penetrations in the device. This report discusses the impact of a major penetration on the design and operation of the pellet injection system in the CIT. The pellet injector is a major component, and it has a line-of-sight penetration through the igloo and test cell wall. All current options for maintenance of the injector require hands-on-access. A nuclear analysis has been performed to establish the feasibility of hands-on-access. A coupled Monte Carlo/discrete-ordinates methodology was used to perform the analysis. This problem is characterized by deep penetration and streaming with very large length-to-diameter ratios. Results from this study indicate that personnel access to the pellet injector glovebox is possible. 14 refs., 3 figs., 3 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA). Fusion Engineering Design Center
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6758543
• Report Number(s): ORNL/FEDC-88/1; ON: DE89001144
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
DESIGN
EQUIPMENT
FEASIBILITY STUDIES
GLOVEBOXES
LABORATORY EQUIPMENT
PELLET INJECTION
POWER DENSITY
RADIATION PROTECTION
SHIELDING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
WALL LOADING