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<strong>atw</strong> Vol. 63 (<strong>2018</strong>) | Issue 8/9 ı August/September<br />

474<br />

AMNT <strong>2018</strong> | YOUNG SCIENTISTS' WORKSHOP<br />

corium resulting in a porous rubble<br />

structure that mainly consists of fuel<br />

and control rods. If this porous structure<br />

enters in contact with the right<br />

amount of water acting as moderator,<br />

there is a potential for recriticality.<br />

In order to avoid recriticality and its<br />

adverse consequences, a criticality<br />

evaluation of the debris bed needs to<br />

be carried out.<br />

The conditions of the debris bed<br />

can be very diverse and strongly<br />

depend on the accident scenario. The<br />

criticality safety control of the fuel<br />

debris is a challenge principally due to<br />

the large uncertainty of the fuel debris<br />

conditions (location, geometry, composition,<br />

temperature, etc.). Severe<br />

accident codes are able to simulate the<br />

accident progression and can be used<br />

to estimate the debris bed conditions,<br />

however, an adequate observation,<br />

sample taking and analysis of the real<br />

fuel debris are crucial to perform an<br />

accurate criticality evaluation.<br />

Due to the high uncertainty of fuel<br />

debris properties, it is necessary to<br />

prepare a comprehensive and extensive<br />

database, which embraces criticality<br />

data of any possible debris bed.<br />

The main factors on the criticality<br />

evaluation of the fuel debris after a SA<br />

are listed below:<br />

• Total amount of corium<br />

• Composition of corium<br />

• Fuel debris geometry<br />

• Coolant conditions<br />

3 Calculation model<br />

3.1 Geometrical model<br />

of the debris bed<br />

Figure 1 shows the conceptual<br />

geometric model of the debris bed<br />

for the Monte Carlo criticality calculations.<br />

The innermost region of the<br />

model represents the debris itself, as a<br />

porous structure consisting of fuel<br />

| | Fig. 1.<br />

Geometric model of debris bed.<br />

Parameter Range Boundary value<br />

Particle size 1 to 14 mm 10.7 mm<br />

Porosity 0.32 to 0.8 Optimum Porosity<br />

Water void fraction 0 to 90 % 0<br />

Fuel burnup 0 to 60 GWd/t HM<br />

25.8 GWd/t HM<br />

(accident conditions)<br />

Debris bed size 10 to 200 cm 200 cm<br />

Water boration 0 to 2,000 ppm B 0<br />

| | Tab. 1.<br />

Criticality parameters and ranges.<br />

particles and water. For conservative<br />

results, the shape of the debris was<br />

spherically arranged minimizing the<br />

neutron leakage and the critical mass.<br />

Surrounding the fuel debris there is a<br />

water reflector of effectively infinite<br />

thickness (approx. 30 cm). Such configuration<br />

was already used for a<br />

criticality safety evaluation for the<br />

TMI-2 safe fuel mass limit [5].<br />

Debris beds comprise particles of<br />

different shapes and sizes, which are<br />

chaotically arranged in the space. In<br />

order to reduce the computational<br />

effort for the criticality calculations,<br />

some simplifications have been<br />

applied to model the porous structure<br />

of the debris: the particles were<br />

assumed to be spherical, all the particles<br />

were assumed to have the same<br />

size and the particles were assumed to<br />

be regularly distributed in the space<br />

following a Body Centered Cubic<br />

(BCC) lattice [6].<br />

3.2 Corium composition<br />

In this study, the Unit 1 of Fukushima<br />

Daiichi NPP was used as reference<br />

[7, 8].<br />

Conservatively, it was assumed<br />

that there was nothing present in the<br />

fuel debris but fuel pellets and water.<br />

Thus, the negative reactivity effects<br />

due to the possible presence of cladding,<br />

fixed absorbers and structural<br />

materials are ignored. As boundary<br />

conditions, room temperature and a<br />

fuel density of 10.4 g/cm 3 are considered.<br />

ORIGEN 2.1 [9] was used to calculate<br />

the radionuclide inventory for<br />

different average burnups, from fresh<br />

fuel up to a burnup of 60 GWd/t HM .<br />

The average burnup in the reactor of<br />

Unit 1 at the moment of the accident<br />

was calculated to be 25.8 GWd/t HM<br />

[8] and was used as reference model.<br />

To perform the burnup calculations,<br />

fresh fuel UO 2 with an initial enrichment<br />

of 3.7 % wt 235 U was irradiated<br />

considering a specific power of<br />

20 MW/t HM in the reactor.<br />

3.3 Coolant composition<br />

Light water is used as moderator. The<br />

density of the water (or void fraction)<br />

was varied to analyse the influence on<br />

the neutron multiplication factor.<br />

Additionally, boron was added in<br />

every scenario in order to know the<br />

required concentration that guarantee<br />

a subcritical condition of the<br />

debris. Room temperature was considered<br />

for all the calculations.<br />

4 Criticality calculations<br />

Criticality calculations have been<br />

performed for multiple scenarios<br />

using the calculation model described<br />

before. Six parameters have been considered<br />

for these calculations: particle<br />

size, porosity, water void fraction, fuel<br />

burnup, debris size and water boration.<br />

The parameters and ranges of<br />

variation are resumed in Table 1.<br />

In order to analyse all the possible<br />

dependencies between these parameters,<br />

they all have been combined by<br />

pairs, resulting in 15 possible combinations<br />

or calculations sets. In each<br />

calculation set, the paired parameters<br />

have been varied over their whole<br />

ranges, giving to the rest of parameters<br />

a boundary value. The neutron multiplication<br />

factor k eff was then calculated<br />

for all the possible combinations. All<br />

the boundary values have been chosen<br />

to be conservative, except the burnup,<br />

where the value at the moment of<br />

AMNT <strong>2018</strong> | Young Scientists' Workshop<br />

A Preliminary Conservative Criticality Assessment of Fukushima Unit 1 Debris Bed ı María Freiría López, Michael Buck and Jörg Starflinger

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