atw 2018-05v6
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<strong>atw</strong> Vol. 63 (<strong>2018</strong>) | Issue 5 ı May<br />
DECOMMISSIONING AND WASTE MANAGEMENT 320<br />
Access gallery<br />
Access gallery<br />
disposal area (1 cluster)<br />
waste batches<br />
disposal area (1 cluster)<br />
waste batches<br />
| | Fig. 1.<br />
Spatial layout for (a) configuration C a and (b) configuration C b . The disposal area can be divided in more<br />
than one cluster. Red: center batch of cluster.<br />
unlimited in time, has recently been<br />
considered by the Nuclear Energy<br />
Agency [OECD-NEA 2012] and is<br />
required by national law in an increasing<br />
number of countries (e.g. Finland,<br />
Germany, Switzerland). As temperatures<br />
increase fast after waste<br />
emplacement, the ambient conditions<br />
for waste retrieval give rise to operational<br />
uncertainties, which should be<br />
taken into account in an early stage of<br />
planning [Heierli and Genoni 2017].<br />
Last but not least, it has been pointed<br />
out that hotter repository designs are<br />
intrinsically more complicated and<br />
that their uncertainties in behaviour<br />
are too large to accept [Long and<br />
Ewing 2004; Whipple et al. 1999].<br />
The trade-offs and uncertainties<br />
are to be analysed in safety cases. The<br />
purpose of the safety cases is to<br />
determine whether an adequate level<br />
of confidence in safety can be achieved<br />
and whether the safety criteria can be<br />
fulfilled [IAEA 2012]. An important<br />
aspect hereby is that the temperature<br />
of components remains within boundaries<br />
determined in safety analyses.<br />
Formally, this step is handled by using<br />
criteria of admissibility in the form of<br />
inequalities [e.g. Hökmark et al. 2009;<br />
Eikemeier et al. 2013; Ikonen and Raiko<br />
2012; Jobmann et al. 2016; Kommission<br />
Lagerung hoch radioaktiver Abfallstoffe<br />
2016]. Unilateral criteria do no<br />
bring about a unique solution, however,<br />
but a scope of admissible choices.<br />
To select amongst those, the prevailing<br />
procedure is to take into account<br />
the use of spatial resources underground,<br />
resulting in setting the space<br />
requirements as high as judged necessary<br />
and as low as judged possible.<br />
drifts (n)<br />
(a)<br />
(b)<br />
drifts (n)<br />
D1<br />
D2<br />
D1<br />
D2<br />
Currently, many national disposal<br />
programmes are in the stage of siteselection.<br />
In this stage, site boundaries<br />
are determined under the leadership<br />
of national governments. In order<br />
clarify the challenges of the corresponding<br />
decision-making process,<br />
this contribution explores the interdependence<br />
between spatial and<br />
thermal dimensioning. Temperatureaffecting<br />
design options are parameterised<br />
to evaluate their benefit on<br />
the one side and the engineering<br />
effort to realise that benefit on the<br />
other. It is emphasised that neither the<br />
optimisation of peak temperatures nor<br />
the optimisation of spatial resources<br />
are the primary objectives of nuclear<br />
waste disposal. It is understood<br />
Project leadership<br />
| | Tab. 1.<br />
Baseline configuration of study cases (10,15). SF = “spent fuel.”<br />
P2<br />
20 m<br />
0.88 m<br />
P3<br />
P1<br />
1.5 m<br />
throughout this work that the main<br />
objective is to enhance both the safe<br />
confinement of waste and the confidence<br />
in the functionality of its<br />
elements.<br />
Materials and method<br />
The configuration of a repository for<br />
high-level waste and spent fuel can be<br />
represented by a configuration vector<br />
C = (x 1 , x 2 , …) of engineering parameters<br />
x i (Figure 1). In the present<br />
context, of interest are those that<br />
affect temperatures most. These are:<br />
the cooling time from reactor retrieval<br />
to disposal of the waste (t cool ), the<br />
number of fuel elements per waste<br />
batch (k), the spacing of disposal<br />
drifts (D 1 ), the spacing of batches<br />
within a drift (D 2 ), the number of<br />
disposal drifts (n) and the size of<br />
sub-clusters of batches for disposal<br />
(s). Parameters that are not freely<br />
adjustable by the engineers, such as<br />
the total amount of waste to be<br />
disposed or the depth of the repository,<br />
are not varied in this study.<br />
Let P i be a decision point for the<br />
dimensioning of temperature in a<br />
component indexed i, e.g. the canister<br />
core, the canister surface, the backfill<br />
material, the ambient rock, the<br />
nearest significant aquifer, etc. For<br />
each P i , there exists a decision<br />
criterion T 0 (P i ) + u(t, P i ) < T i , where<br />
T 0 (P i ) is the undisturbed temperature<br />
at P i , u(t, P i ) is the temperature<br />
increase at P i at time t. The right-hand<br />
side term T i is the admissible boundary<br />
temperature for the component<br />
at P i . A configuration C = (n, t cool , k,<br />
D 1 , D 2 , s, …) is considered admissible<br />
if the criterion is satisfied for all P i .<br />
symbol<br />
C a<br />
Nagra<br />
C b<br />
Posiva<br />
Type of host rock (fixed) clay crystalline<br />
Depth of the repository (fixed) 650 m 420 m<br />
SF type (fixed) UO 2 +MOX UO 2<br />
burnup (fixed) 48 MWd/kg 40 MWd/kg<br />
Cooling time of SF t cool 55 y 33 y<br />
Initial average decay power per SF element π 0 (t cool ) 337.5 W 189 W<br />
Number of SF elements for disposal (fixed) F 8748 8100<br />
Number of SF elements per batch k 4 9<br />
Initial average decay power per waste batch p 0 = kπ 0 1350 W 1700 W<br />
Number of disposal drifts n 27 30<br />
Number of batches per disposal drift m 81 30<br />
Number of batches total N= F/k = nm 2187 900<br />
Spacing of disposal drifts D 1 40 m 25 m<br />
Spacing of batches within a drift D 2 7.6 m 8.92 m<br />
Cluster size s 27×81 30×30<br />
Decommissioning and Waste Management<br />
Scope for Thermal Dimensioning of Disposal Facilities for High-level Radioactive Waste and Spent Fuel ı Joachim Heierli, Helmut Hirsch, Bruno Baltes