ITER physics-safety interface: models and assessments

Conference · Tue Oct 01 00:00:00 EDT 1996

OSTI ID:394467

Uckan, N A ^[1]; Putvinski, S; Wesley, J; Bartels, H-W ^[2]; Honda, T ^[3]; Amano, T ^[4]; Boucher, D; Fujisawa, N; Post, D; Rosenbluth, M ^[2]

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1. Oak Ridge National Lab., TN (United States)
2. ITER San Diego Joint Work Site, CA (United States)
3. Hitachi Ltd., Ibaraki (Japan). Hitachi Research Lab.
4. National Inst. for Fusion Science, Nagoya (Japan)

Plasma operation conditions and physics requirements to be used as a basis for safety analysis studies are developed and physics results motivated by safety considerations are presented for the ITER design. Physics guidelines and specifications for enveloping plasma dynamic events for Category I (operational event), Category II (likely event), and Category III (unlikely event) are characterized. Safety related physics areas that are considered are: (i) effect of plasma on machined and safety (disruptions, runaway electrons, fast plasma shutdown) and (ii) plasma response to ex-vessel LOCA from first wall providing a potential passive plasma shutdown due to Be evaporation. Physics models and expressions developed are implemented in safety analysis code (SAFALY, couples 0-D dynamic plasma model to thermal response of the in-vessel components). Results from SAFALY are presented.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• OSTI ID: 394467
• Report Number(s): CONF-9606116-81; ON: DE96014608; TRN: 97:000018
• Resource Relation: Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: [1996]
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION
ITER TOKAMAK
SAFETY ANALYSIS
S CODES
LOSS OF COOLANT
RISK ASSESSMENT
PLASMA DISRUPTION
RUNAWAY ELECTRONS
EMERGENCY PLANS
DESIGN BASIS ACCIDENTS