Design Basis Accident Summary

The previous sections have discussed a number of possible CDA initiators. All of them have been shown to be most unlikely, and all but two may be ruled out as initiators. Attention would naturally be given to their absolute design prohibition. The two accidents that were not ruled out but further discussed were the local failure that might arise from an overenriched pin

Loss of Cooling with Failure to scram

Time, seca

Fuel behavior

Channel and power behavior

0.0

Normal full power. Loss of electrical supply to pumps and reduction in flow

0.9

Failure to scram following loss of supply signal

0.95

Fuel cladding begins to overheat

Failure to scram following low flow signal

6.5

Sodium boiling in hottest chan­nels; voiding pressures about 50 psia

6.56

Boiling in next annulus and succeeding annuli radially outwards through core; re­activity rises

6.95

Prompt criticality from sodium voiding reactivity; rate$5/sec

7.3

Large regions of the fuel are molten due to the excursion. The sodium film left on the cladding vaporizes, increasing local pressures; fuel tempera­tures up to 3500°K

Internal pressures disassemble the core just enough to shut down. The disassembly would result in a few inches of axial movement of fuel

7.4

Fuel commences to slump under gravity depending on the distri­bution of molten fuel in each annulus of the core; reactivity rises

High assembly pressures due to film vaporization (about 4000 psia) maintain dry assembly conditions

7.45

Prompt criticality is attained at a rate of 30-50f/sec; power excursion

7.5

Work energy release of 200-500 (say 500) MW-sec depending on the amount of sodium in the core. Pressures in the fuel about 1000 psia

Shut-down. The core fuel is dispersed in the vessel

TABLE 5.10 (continued)

Time, sec0

Fuel behavior

Channel and power behavior

7.5

Fuel and structure dispersed through the sodium above the core. Outer assemblies will be deformed by shock and will absorb some energy

Shock to vessel strains it up to 1 % and relieves pressures by increased volume. Approxi­mately 5% of energy absorbed

7.57

Fuel slumps through debris, freezing and melting alternately

Energy transferred to sodium slug which hits the vessel plug as a hammer. Sodium velocity of order of 80-100 ft/sec Hammer energy of order of 30­60 MW-sec

7.6

Vessel plug may lift, releasing gas

0 Times are only intended to be representative of the speed of various effects.

or a blocked channel and the failure to scram in conjunction with another more likely event.

Analysis to date, combined with experiments on fuel-sodium interaction, transient destruction of fuel, and explosive testing of the fuel assembly wrappers, seems to indicate that propagation cannot occur following a local failure and therefore this case also should not be used to provide a CDA.

The scram failure case is analyzed as a direct result of licensing practice. It would be preferable to spend the technical effort in assessing reliability of the scram system, and this may well be done in the future. At that time a design basis for the containment may consist of a fuel handling mishap instead of a core disruptive accident. In that case the containment building will be reduced to the function of a roof for plant components.

A sodium fire is also used to evaluate containment design in many plants. Section 4.5 has shown how the sodium fire is analyzed and how its effect need not be restrictive to the design. Indeed the most sensible design solu­tion is to inert the sodium areas so as to rule out the sodium fire entirely.

In the future, the fast reactor may well consist of a covered rather than a contained plant. This will not be possible until a breakthrough comes in the analysis of initiating events or in the experimental program carried out in support of that analysis. Such a breakthrough will have to be accompanied by a breakthrough in the licensing attitude at the same time.