Caple AUF900 Uživatelský manuál stáhnout pdf (Strana 151)

149

ENSI Erfahrungs- und Forschungsbericht 2011

ported by scientific specialists and technical staff

from the Laboratory for Nuclear Materials (LNM)

and Hot Laboratory Division (AHL) at PSI (Compo-

nent Safety (BTS), Isotope and Elemental Analysis

(IEA) and Nuclear Fuels (NF) groups). NORA is pl-

anned as a 3.5 years project. KKL and KKM provi-

de relevant in-kind contributions (e.g., by granting

access to information and the possibility to expo-

se flat and cracked specimens in KKL’s mitigation

monitoring system and reactor water sample line).

The focus of the second project year was the op-

timisation of the experimental set-up, a first series

of Pt deposition experiments (eight tests) and an

assessment of the analytical techniques which are

used to analyse the Pt distribution on the speci-

mens. In the following chapter results of the first

two experiments are briefly described and an ex-

ample of the Pt distribution on a specimen from

the latest experiment is shown.

3. Results from the first

experiments

There are several aspects which are probably rele-

vant for the Pt distribution and deposition behavi-

our on the water-wetted steel surfaces in a BWR.

Some of these points of interest are: amount, con-

centration and injection rate of the Pt injected into

the feed water; flow velocity of the water on the

Pt treated steel surfaces; temperature of the feed

and reactor water; redistribution behaviour of the

Pt particles; concentration of iron-particles/crud in

the feed and reactor water; surface conditions of

the steel (roughness, oxide layer, etc.); penetrati-

on depth of Pt into cracks as a function of crack

opening, crack path (intergranular vs. transgra-

nular) and flow rate; etc. In the first two experi-

ments the effect of Pt injection rate and pre-oxi-

dation time on the ECP and Pt deposition on stain-

less steel specimens were investigated. The results

of these tests and a SEM micrograph of the latest

experiment are briefly presented in the following

sub-chapters.

3.1. Material and specimens

For the investigation of the Pt deposition behavi-

our a type 304L stainless steel (UNS S30403) from

an original pipe from a nuclear power plant was

chosen [13]. Coupons (13 × 10 × 4 mm) with a de-

fined surface roughness (R

0.3 μm) were used

for the experiments. The specimens were either

pre-oxidised for about 310 h in HWC environment

or used in the «as received» state.

3.2. Experimental procedure

The Pt deposition tests were performed in a so-

phisticated high-temperature water loop with 1 l

stainless steel autoclave (Figure 1). During the ex-

periments all environmental parameters at inlet

Figure 1:

Schematic of the

high-temperature

water loop facility.

1 2 ... 146 147 148 149 150 151 152 153 154 155 156 ... 303 304

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