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The Risk Assessment task for the FSP was initially created to appraise the processes of probabilistic safety assessment (PSA) and utilize these processes for fusion safety assessments. With this definition, the primary focus of the task was public safety. The scope of the task has since expanded to include the issues of reliability in design, worker safety, and environmental pollution.

In the PSA field, it is imperative to remain abreast of recent progress in the fields of risk-modeling computer codes, dose-consequence assessment computer codes, and the input data requirements of these codes. Thus, we actively monitor the latest developments in these areas and provide feedback or interactions with the computer code developers when possible.

For the program's work with PSA's, it is imperative to remain abreast of recent progress in the fields of risk-modeling computer codes, dose-consequence assessment computer codes, and the input data requirements of these codes. Thus, the Fusion Safety Program actively monitors the latest developments in these areas and tries to provide feedback or interactions, when possible.

Under the guidelines of the Risk Assessment task, we have made significant safety and environmental assessment contributions to the fusion experiments at the Princeton Plasma Physics Laboratory:

• Environmental and safety analyses for the Fusion Ignition Research Experiment (FIRE),
• Safety Analysis Report for the Tokamak Physics Experiment (INEL-95/0199),
• Off-normal events for the Tokamak Physics Experiment (EGG-FSP-10710),
• Environmental Assessment for Tokamak Fusion Test Reactor Decontamination and Decommissioning and Tokamak Physics Experiment Construction (DOE/EA-0813),
• Accident risk assessment for TFTR D&D (EGG-FSP-10682).

Our Risk Assessment task also supports fusion design study activities. Some examples of the work that we have contributed to fusion design studies include:

• ITER safety support for accident identification, analysis, and personnel safety,
• Component failure data for safety assessment tasks (INEEL/EXT-98-00892),
• Initial safety assessment of flibe for fusion reactors (INEL/EXT-99-00331),
• Qualitative reliability issues for solid and liquid wall fusion designs (INEEL/EXT-2000-1367),
• Risk assessment tasks for inertial fusion energy plant designs are in progress.

Our Risk Assessment task makes an important contribution to the collection and establishment of component reliability data for fusion devices. The collection and analysis of these data is critical for (1) validating existing and newly developed risk models and (2) performing fusion safety analyses and PSAs. The following is a summary of our contributions to the fusion community's work with component reliability data:

The following is a summary of the Fusion Safety Program's contributions to the fusion community's effort on the acquisition and analysis of component reliability data:

• Compiled data from published literature on
  • magnet systems (EGG-FSP-9977),
  • cryogenic systems (EGG-FSP-10048),
  • vacuum systems (EGG-FSP-11037),
  • in-vessel tubing systems (EGG-FSP-10928),
  • ventilation systems (INEEL/EXT-99-001318).
• Analyzed data from several support systems at the Los Alamos Tritium Systems Test Assembly (TSTA) These data were shown to compare favorably with data from other tritium laboratories (Fusion Engineering and Design, 54, April 2001, pages 353-359). The TSTA data included:
  • nitrogen gas handling system,
  • tritium monitoring systems,
  • gloveboxes,
  • air detritiation system
• Studied the reliability of fire suppression systems (INEL-95/0396) and sensor elements (INEL-96/0295).