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SUMMARY OF REACTOR AND PASSIVE SAFETY SYSTEM CATEGORIES
The characterization of the nuclear reactor designs based on the passive (sub-) systems constitutes the objective of the present section. This can be achieved by combining the reactor descriptions given in Annexes I to XX and the passive systems identified in Sections 2 and 3. Furthermore, the ‘passive’ thermal-hydraulic phenomena characterized in Section 4 can be cross-correlated with the reactor configurations.
|
Type of Passive Safety System |
Passive Safety Systems of Advanced Designs |
Related Phenomena |
|
Pre-pressurized Core Flooding Tanks (Accumulators)[1] — Section 2.1 — |
Accumulators (AP-1000) ECCS accumulator subsystem (WWER-640/V-407) First stage hydro-accumulators (WWER-1000/V-392) Advanced accumulators (APWR+) Standby liquid control system (ESBWR) Accumulator (AHWR) |
8,2,5 |
|
Emergency core coolant tanks (SMART) |
||
|
Elevated Tank Natural Circulation Loops (Core Make-up Tanks) — Section 2.2 — |
Core make-up tanks (AP-1000) Second stage hydro-accumulators (WWER-1000/V-392) Core make-up tanks (ACR-1000) Core make-up tanks (SCWR-CANDU) Emergency boration tanks (IRIS) |
8,6,9,5,15 |
|
Elevated Gravity Drain Tanks — Section 2.3 — |
Core flooding system (SWR 1000) IRWST injection (AP-1000) ECCS tank subsystem — Elevated hydro-accumulators open to the containment (WWER-640/V-407) Gravity-driven cooling system (SBWR and ESBWR) Suppression pool injection (SBWR and ESBWR) Gravity-driven core cooling system (LSBWR) Gravity-driven water pool (GDWP) injection (AHWR) Reserve water system (ACR-1000) Reserve water system (SCWR-CANDU) |
8,5 |
|
Containment suppression pool injection (IRIS) |
||
|
Passively Cooled Steam Generator Natural Circulation (water cooled) — Section 2.4 — |
SG passive heat removal system (WWER-640/V-407) Passive residual heat removal system (SMART) Emergency decay heat removal system (PSRD) Stand-alone direct heat removal system (IMR) Passive emergency heat removal system (IRIS) |
13,1,6 |
|
Passively Cooled Steam Generator Natural Circulation (air cooled) |
Passive residual heat removal system via SG (WWER- 1000/V-392) Passive core cooling system using SG — open loop (APWR+) |
6,4 |
|
— Section 2.4 — |
Stand-alone direct heat removal system — late phase (IMR) |
|
|
Passive Residual Heat Removal Heat Exchangers — Section 2.5 — |
Passive residual heat removal system (AP-1000) Passive moderator cooling system — inside insulated PT without CT (SCWR-CANDU) Residual heat removal system on primary circuit (SCOR) |
13,6,2,1 |
|
Passively Cooled Core Isolation Condensers — Section 2.6 — |
Emergency condensers (SWR 1000) Isolation condenser system (SBWR and ESBWR) Passive reactor cooling system (ABWR-II) Isolation condenser (RMWR) Isolation condenser (AHWR) Residual heat removal system (CAREM) |
13,6,1 |
|
Sump Natural Circulation — Section 2.7 — |
Lower containment sump recirculation (AP-1000) Primary circuit un-tightening subsystem (WWER-640/V — 407) ADS-steam vent valves and submerged blow-down nozzles (MASLWR) |
6,1 |
|
Containment Pressure Suppression Pools — Section 3.1 — |
ADS 1-3 steam vent into IRWST (AP-1000) Automatic depressurization through safety relief valves — vent into suppression pool (SBWR and ESBWR) Steam vent into suppression pool through SRV and DPV (LSBWR) Steam vent into suppression pool through safety valves (CAREM) Steam dump pool (SCOR) Containment pressure suppression system (SCOR) Steam vent into suppression pool through ADS (IRIS) |
1,7,3 |
|
Containment Passive Heat Removal/Pressure Suppression Systems (Steam Condensation on Condenser Tubes) — Section 3.2 — |
Containment cooling condensers (SWR 1000) Passive containment cooling system (AHWR) |
4,1,2,3 |
|
Containment Passive Heat Removal/Pressure Suppression Systems (External Natural Circulation Loop) — Section 3.2 — |
Containment passive heat removal system (WWER-640/V — 407) Containment water cooling system (PSRD) |
4,1,2,3 |
|
Containment Passive Heat Removal/Pressure Suppression Systems (External Steam Condenser Heat Exchanger) — Section 3.2 — |
Passive containment cooling system (SBWR and ESBWR) Passive containment cooling system (ABWR-II) Passive containment cooling system (RMWR) |
4,1,2,3 |
|
Passive Containment Spray Systems — Section 3.3 — |
Passive containment cooling system (AP-1000) Passive containment cooling system (LSBWR) Containment cooling spray (ACR-1000) Containment cooling spray (SCWR-CANDU) |
3,2,4 |
(a) PWR, BWR and SCWR (Super Critical Water Cooled Reactor) systems, Annexes I to XIII;
(b) Integral Reactor Systems, Annexes XIV to XX.
The main information in Tables 3 and 4 connects the reactor type with the passive safety systems, e. g. column 1 and 4. Thermal-hydraulic phenomena are cross-connected with specific passive safety systems in columns 4 and 5. Finally columns 2 and 3 provide elements, as an example, namely the thermal power and the ‘boiling’ or ‘pressurized’ feature, that characterize the reactor system.
‘Proven’ technology reactors, i. e. with final design already scrutinized in a formal safety review process, or under construction, or with an already built and operated prototype, are listed in Table 3, with a few exceptions constituted by the RMWR, the LSBWR and the SCWR that are at different levels of early design stages.
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TABLE 3. PWR, BWR AND SCWR SYSTEMS AND TYPES OF PASSIVE SAFETY SYSTEMS
|
|
Advanced PWR (APWR+) Mitsubishi, Japan |
PWR |
5000 |
Passive Core Cooling System using Steam Generator |
6,4 |
|
Advanced Accumulators |
8,2,5 |
|||
|
Simplified Boiling Water Reactor (SBWR) General Electric, USA |
BWR |
2000 |
Gravity Driven Cooling System |
8,5 |
|
Suppression Pool Injection |
8,5 |
|||
|
Isolation Condenser System |
13,6,1 |
|||
|
Passive Containment Cooling System |
4,1,2,3 |
|||
|
ADS-SRV Vent into Suppression Pool |
1,7,3 |
|||
|
Economic Simplified Boiling Water Reactor (ESBWR) General Electric, USA |
BWR |
4500 |
Gravity Driven Cooling System |
8,5 |
|
Suppression Pool Injection |
8,5 |
|||
|
Isolation Condenser System |
13,6,1 |
|||
|
Standby Liquid Control System |
8,2,5 |
|||
|
Passive Containment Cooling System |
4,1,2,3 |
|||
|
ADS-SRV Vent into Suppression Pool |
1,7,3 |
|||
|
Advanced BWR (ABWR-II) Tokyo Electric Power Company (TEPCO), General Electric, Hitachi and Toshiba, Japan |
BWR |
4960 |
Passive Reactor Cooling System |
13,6,1 |
|
Passive Containment Cooling System |
4,1,2,3 |
|||
|
Reduced-Moderation Water Reactor (RMWR) Japan Atomic Energy Agency (JAEA), Japan |
BWR |
3926 |
Isolation Condenser System |
13,6,1 |
|
Passive Containment Cooling System |
4,1,2,3 |
|||
|
Advanced Heavy Water Reactor (AHWR) Bhabha Atomic Research Centre, India |
HWR |
750 |
Gravity Driven Water Pool Injection |
8,5 |
|
Isolation Condenser System |
13,6,1 |
|||
|
Accumulator |
8,2,5 |
|||
|
Passive Containment Cooling System |
4,1,2,3 |
|||
|
Advanced CANDU Reactor (ACR 1000) Atomic Energy of Canada Ltd, Canada |
HWR |
3180 |
Core Make-up Tanks |
8,6,9,5,15 |
|
Reserve Water System (RWS) |
8,5 |
|||
|
Containment Cooling Spray |
3,2,4 |
|||
|
Long operating cycle Simplified Boiling Water Reactor (LSBWR) Toshiba, Japan |
BWR |
900 |
Gravity Driven Core Cooling System |
8,5 |
|
Passive Containment Cooling System |
3,2,4 |
|||
|
Steam Vent into Suppression Pool through SRV and DPV |
1,7,3 |
|||
|
SCWR-CANDU Atomic Energy of Canada Ltd, Canada |
SCWR |
2540 |
Core Make-up Tanks |
8,6,9,5,15 |
|
Reserve Water System |
8,5 |
|||
|
Passive Moderator Cooling System |
13,6,2,1 |
|||
|
Containment Cooling Spray |
3,2,4 |
As a difference from the reactors listed in Table 3, all the integral reactor systems in Table 4 are in a design stage and no-one of such design has undergone a comprehensive safety scrutiny process (i. e. the licensing). However, in some cases, e. g. CAREM and to a lower extent IRIS, the reactor systems are under design since couple of decades, thus testifying the technological difficulties encountered for the exploitation of the integral nuclear reactor configuration idea.
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TABLE 4. INTEGRAL REACTOR SYSTEMS AND TYPES OF PASSIVE SAFETY SYSTEMS
|
Passive systems are widely considered in ‘innovative’ or advanced nuclear reactor designs and are adopted for coping with critical safety functions. The spread and the variety of related configurations are outlined in the present document.
Twenty ‘innovative’ nuclear reactors are described, specially giving emphasis to the passive safety systems, in the annexes and distinguished in two groups; (see also Tables 3 and 4):
• Advanced water cooled nuclear power plants,
• Integral reactor systems.
The levels of development, or even the actual deployment of the concerned reactor designs (i. e. equipped with passive systems) for electricity production are very different, and the range of maturity of these extend from reactors already in operation to preliminary reactor designs which are not yet submitted for a formal safety review process.
A dozen different passive system types, having a few tens of reactor specific configurations, suitable to address safety functions in primary loop or in containment have been distinguished, as in Table 2. These include systems like the core make-up tanks, the containment spray cooling and the isolation condenser.
The thermal-hydraulic performance of the passive systems has been characterized by less than a dozen key phenomena at their time characterized through specific descriptions including a few tens of relevant thermal-hydraulic aspects, see Table 1 and the Appendix. Cross correlations between key thermal-hydraulic phenomena, reactor specific safety systems and ‘innovative’ nuclear plants have also been established (See Tables 2, 3, and 4).
There is the need to demonstrate the understanding of the key thermal-hydraulic phenomena that are selected for characterizing the performance of passive systems: this implies the identification of parameter ranges, the availability of proper experimental programs and the demonstration of suitable predictive capabilities for computational tools.
Comprehensive experimental and code development research activities have been conducted, also very intensely at an international level, in the past three to four decades in relation to the understanding of thermal-hydraulic phenomena and for establishing related code predictive capabilities for existing nuclear power reactors. In the same context, research activities also addressed some of the phenomena for passive systems. However, a systematic effort for evaluating the level of understanding of thermal-hydraulic phenomena for passive systems and connected code capabilities appears to be limited and in general lacking.
Appendix