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<strong>atw</strong> Vol. 60 (<strong>2<strong>01</strong>5</strong>) | Issue 1 ı January<br />

ENERGY POLICY, ECONOMY AND LAW 28<br />

| | Fig. 1.<br />

Strategy of GSR Development for SFR.<br />

Art. Title Art. Title Art. Title<br />

1 Definition 21 Use of qualified equipment 41 I&C system<br />

2 Radiation Protection 22 Human factors 42 Electric power system<br />

3 Defense-in-Depth 23 Prevention of harmful effects<br />

between systems<br />

4 Interfaces of safety with<br />

security and safeguards<br />

5 Physical Protection / Safeguards<br />

24 Protection against sodium<br />

reactions<br />

6 Proven technologies 26 Inherent protection of<br />

reactor<br />

| | Tab. 1.<br />

General Safety Requirements (Articles of Technical Standards) for SFR.<br />

43 Control room, etc.<br />

44 Alarm devices, etc.<br />

25 Reactor design 45 Optimization of radiation<br />

protection<br />

7 Assessment of Design Safety 27 Suppression of reactor power<br />

oscillation<br />

8 Construction and operating<br />

experiences<br />

46 Radioactive waste processing<br />

& storage systems<br />

47 Radiation protection<br />

provision<br />

28 Reactor core, etc. 48 Fuel handling & storage<br />

facilities<br />

9 Decommissioning 29 Fuel rod and assembly 49 Auxiliary systems<br />

10 Postulated initiating events 30 Protection against flow<br />

blockage<br />

50 Power conversion system<br />

11 Design bases accidents 31 Reactivity control system 51 Emergency response facilities<br />

and equipment<br />

12 Design extension conditions 32 Reactor protection system 52 Intermediate cooling system<br />

13 Safety classes and standards 33 Use of computerized system 53 Liquid sodium handling<br />

system<br />

14 External events design bases 34 Diverse protection system 54 Sodium heating system<br />

15 Fire protection 35 Reactor coolant boundary 55 Protection against sodium<br />

freezing<br />

16 Design bases for environmental<br />

effects<br />

36 Reactor cooling system 56 Purification control of cover<br />

gas and supply<br />

17 Reliability 37 Overpressure protection 57 Operating experiences and<br />

safety research<br />

18 Sharing of facilities 38 Residual heat removal<br />

system<br />

19 calibration / test / inspection/<br />

maintenance<br />

20 Startup, shutdown, and low<br />

power operation<br />

58 Limiting conditions for<br />

operation<br />

39 Ultimate heat sink 59 Initial tests<br />

40 Reactor containment, etc.<br />

new requirements to be added, we<br />

have referenced the international documents<br />

like IAEA SSR-2/1, Safety Design<br />

Criteria of GIF and draft version<br />

of SFR GDC under development by<br />

ANS. Fukushima action items and applicability<br />

of Risk Informed Regulation(RIR)<br />

are also considered. Utilizing<br />

this strategy and process, we have<br />

developed a draft version of SFR GSR<br />

containing 59 articles. The title of the<br />

articles are listed in Table 1.<br />

3. Development of OPT for<br />

SFR reactivity control<br />

safety function<br />

The OPT is a top-down method with a<br />

tree structure for each DID level describing<br />

objectives and barriers, safety<br />

function, challenges to maintain<br />

safety functions, mechanisms of safety<br />

function degradation, and provisions<br />

for each degradation or failure mechanisms<br />

to maintain safety functions.<br />

Reference [2] describes conceptually<br />

how to apply this methodology to development<br />

of safety requirements for<br />

innovative reactors, specifically for<br />

the modular high temperature gas<br />

cooled reactors. In general, we have<br />

three safety functions to fulfill the<br />

safety objectives, i.e., control of reactivity,<br />

core heat removal and containment<br />

integrity. Among these three<br />

safety functions, we have developed<br />

the OPT for the safety function of “reactivity<br />

control”. Because the design of<br />

PGSFR is not mature yet, we have developed<br />

the OPT modelling the KA-<br />

LIMER-600 [4] reactor which is conceptually<br />

designed by KAERI and is an<br />

SFR of 600 MWe size. OPT is a qualitative<br />

methodology whose development<br />

relies mainly on experiences of<br />

experts using the design documents<br />

like probabilistic safety assessment report.<br />

Because the SFR GSR we are developing<br />

is a general one which should<br />

not be reactor or design specific, we<br />

have developed the OPT for KALIMER<br />

even if the target reactor to apply the<br />

GSR in reviewing is the PGSFR. The<br />

detailed description of the system is<br />

not included in this paper since it is not<br />

necessary to understand the developed<br />

OPT. Example of the Level 3<br />

OPT we have developed for the safety<br />

function of “reactivity control” is<br />

shown in Figure 2.<br />

In Figure 2, safety function means<br />

the essential function necessary to ensure<br />

the safety objectives by maintaining<br />

DID and barrier integrity. Challenge<br />

is the phenomenon which<br />

threatens the successful achievement<br />

of the safety function and the possible<br />

challenges to the safety function<br />

Energy Policy, Economy and Law<br />

Assessment of General Safety Requirements for SFR ı Namduk Suh, Moohoon Bae, Yongwon Choi, Bongsuk Kang and Huichang Yang

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