LOFA (loss of flow accident) and LOCA (loss of coolant accident) in the TIBER-II engineering test reactor: Appendix A-4

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:5867702

Sviatoslavsky, I N; Attaya, H M; Corradini, M L; Lomperski, S

This paper describes the preliminary analysis of LOFA (loss of flow accident) and LOCA (loss of coolant accident) in the TIBER-II engineering test reactor breeding shield. TIBER-II is a compact reactor with a major radius of 3 m and thus requires a thin, high efficiency shield on the inboard side. The use of tungsten in the inboard shield implies a rather high rate of afterheat upon plasma shutdown, which must be dissipated in a controlled manner to avoid the possibility of radioactivity release or threatening the investment. Because the shield is cooled with an aqueous solution, LOFA does not pose a problem as long as natural convection can be established. LOCA, however, has more serious consequences, particularly on the inboard side. Circulation of air by natural convection is proposed as a means for dissipating the inboard shield decay heat. The safety and environmental implications of such a scheme are evaluated. It is shown that the inboard shield temperature never exceeds 510/sup 0/C following LOCA posing no hazard to reactor personnel and not threatening the investment. 7 refs., 6 figs.

• Research Organization: Wisconsin Univ., Madison (USA). Fusion Technology Inst.
• DOE Contract Number: FG02-87ER52140
• OSTI ID: 5867702
• Report Number(s): CONF-871007-53; ON: DE88002462
• Resource Relation: Conference: 12. symposium on fusion engineering, Monterey, CA, USA, 12 Oct 1987; Other Information: Paper copy only, copy does not permit microfiche production
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TIBER-X TOKAMAK
LOSS OF COOLANT
LOSS OF FLOW
BREEDING BLANKETS
FIRST WALL
HEAT TRANSFER
LITHIUM
RADIOACTIVITY
SAFETY
SHIELDING
SPECIFIC HEAT
TEMPERATURE DEPENDENCE
THERMAL CONDUCTIVITY
ACCIDENTS
ALKALI METALS
ELEMENTS
ENERGY TRANSFER
METALS
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR COMPONENTS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700206* - Fusion Power Plant Technology- Environmental Aspects
700204 - Fusion Power Plant Technology- Cooling Systems