scholarly journals MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS

2003 ◽  
Author(s):  
M. Ishii ◽  
S. T. Revankar ◽  
T. Downar ◽  
H. J. Yoon Y. Xu ◽  
D. Tinkler ◽  
...  
Keyword(s):  
Reactor Design ◽  
Boiling Water ◽  
Passive Safety ◽  
Boiling Water Reactor ◽  
Full Size ◽  
Water Reactor ◽  
Passive Safety Systems ◽  
Safety Systems

Behaviors of passive safety systems under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor

2015 ◽  
Vol 83 ◽  
pp. 35-42 ◽  
Author(s):  
Jun Yang ◽  
Jaehyok Lim ◽  
Sung Won Choi ◽  
Doo Yong Lee ◽  
Somboon Rassame ◽  
...  
Keyword(s):  
Boiling Water ◽  
Passive Safety ◽  
Boiling Water Reactor ◽  
Feed Water ◽  
Water Line ◽  
Water Reactor ◽  
Passive Safety Systems ◽  
Safety Systems

iB1350: A Generation III.7 Reactor After the Fukushima Daiichi Accident

2016 ◽  
Author(s):  
Takashi Sato ◽  
Keiji Matsumoto ◽  
Kenji Hosomi ◽  
Keisuke Taguchi
Keyword(s):  
Cooling System ◽  
Boiling Water ◽  
Passive Safety ◽  
Active Safety ◽  
Water Reactor ◽  
Airplane Crash ◽  
Passive Safety Systems ◽  
Active Safety Systems ◽  
Fukushima Daiichi ◽  
Safety Systems

iB1350 stands for an innovative, intelligent and inexpensive boiling water reactor 1350. It is the first Generation III.7 reactor after the Fukushima Daiichi accident. It has incorporated lessons learned from the Fukushima Daiichi accident and Western European Nuclear Regulation Association safety objectives. It has innovative safety to cope with devastating natural disasters including a giant earthquake, a large tsunami and a monster hurricane. The iB1350 can survive passively such devastation and a very prolonged station blackout without any support from the outside of a site up to 7 days even preventing core melt. It, however, is based on the well-established proven Advance Boiling Water Reactor (ABWR) design. The nuclear steam supply system is exactly the same as that of the current ABWR. As for safety design it has a double cylinder reinforced concrete containment vessel (Mark W containment) and an in-depth hybrid safety system (IDHS). The Mark W containment has double fission product confinement barriers and the in-containment filtered venting system (IFVS) that enable passively no emergency evacuation outside the immediate vicinity of the plant for a severe accident (SA). It has a large volume to hold hydrogen, a core catcher, a passive flooding system and an innovative passive containment cooling system (iPCCS) establishing passively practical elimination of containment failure even in a long term. The IDHS consists of 4 division active safety systems for a design basis accident, 2 division active safety systems for a SA and built-in passive safety systems (BiPSS) consisting of an isolation condenser (IC) and the iPCCS for a SA. The IC/PCCS pools have enough capacity for 7-day grace period. The IC/PCCS heat exchangers, core and spent fuel pool are enclosed inside the containment vessel (CV) building and protected against a large airplane crash. The iB1350 can survive a large airplane crash only by the CV building and the built-in passive safety systems therein. The dome of the CV building consists of a single wall made of steel and concrete composite. This single dome structure facilitates a short-term construction period and cost saving. The CV diameter is smaller than that of most PWR resulting in a smaller R/B. Each active safety division includes only one emergency core cooling system (ECCS) pump and one emergency diesel generator (EDG). Therefore, a single failure of the EDG never causes multiple failures of ECCS pumps in a safety division. The iB1350 is based on the proven ABWR technology and ready for construction. No new technology is incorporated but design concept and philosophy are initiative and innovative.

Thermal-hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

2021 ◽  
Author(s):  
Satya Prakash Saraswat ◽  
Dipanjan Ray ◽  
Gaurav Mishra ◽  
Deepak Yadav ◽  
Vikesh Singh Bhadouria ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Reactor Design ◽  
Full Scale ◽  
Boiling Water ◽  
Electricity Production ◽  
Passive Safety ◽  
Passive Safety Systems ◽  
The Us ◽  
Accident Conditions ◽  
Safety Systems

Abstract The Economic Simplified Boiling Water Reactor (ESBWR) is a boiling water nuclear reactor of Generation III+. The US Nuclear Regulatory Commission (NRC) approved the ESBWR design as the world's best light-water nuclear reactor in 2014. It has the lowest core damage frequency (industry standard indicator of safety) of any Generation III or III+ reactor. It can cool automatically for more than seven days without using electricity or human intervention. During the operation, the ESBWR is designed to produce electricity while emitting almost no greenhouse gases. The energy generated by an ESBWR will prevent the emission of approximately 7.5 million metric tons of CO2 per year compared to standard electricity production on the US grid. The analysis present in this paper aimed to characterize the thermal-hydraulic simulations of full-scale ESBWR design. The analysis presented will help in recognizing the improvement needed in the reactor design and its passive safety systems. The analysis is performed for normal steady state and postulated design basis accident scenarios . The simulation results obtained by the code REALP/SCDAPSIM/MOD3.4 are compared with the TRACG and MELCOR code results to determine the code predictability and accuracy under accident conditions of the newly proposed design of the ESBWR nuclear reactor. It has been also demonstrated that for the postulated accident conditions the design of passive safety systems are capable to capture the accident progression without any active power.

Enhancement of Plant Availability by Outage Shortening in European Advanced Boiling Water Reactor (EU-ABWR)

2013 ◽  
Author(s):  
Kazuhiro Kamei ◽  
Kazuyoshi Kataoka ◽  
Kazuto Imasaki ◽  
Noboru Saito
Keyword(s):  
Boiling Water ◽  
Severe Accident ◽  
Boiling Water Reactor ◽  
Plant Availability ◽  
Control Rod ◽  
Water Reactor ◽  
Spray System ◽  
Maintenance And Inspection ◽  
Reactor Pool ◽  
Safety Systems

European Advanced Boiling Water Reactor (EU-ABWR) is developed by Toshiba. EU-ABWR accommodates an armored reactor building against Airplane Crash, severe accident mitigation systems, the N+2 principle in safety systems, the diversity principle and a large output of 1600 MWe. These features enable EU-ABWR’s design objectives and principles to be consistent with the requirements in the Finnish utility and the safety requirements of Finnish YVL guide. By adopting Scandinavian outage processes, the Plant Availability is aimed to be greater than 95%. ABWRs have an excellent design potential to acheive short outage duration (e.g., shortening of maintenance and inspection duration by applying Fine Motion Control Rod Drive and Reactor Internal Pump). In addition, the EU-ABWR applies following key design improvements to reduce a refueling outage duration; a) Direct Reactor Pressure Vessel (RPV) Head Spray System, b) Self-standing Control Rods and c) Water shielding reactor pool. In this paper, coolability of RPV due to application of the Direct RPV Head Spray System is also verified with numerical evaluations by Computation Fluid Dynamics (CFD) analysis.

Design of Compact and Full-Size Simplified Boiling Water Reactors With Fully Passive Safety Systems

2002 ◽  
Author(s):  
M. Ishii ◽  
S. T. Revankar ◽  
Y. Xu
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactors ◽  
Scaling Analysis ◽  
Cooling Systems ◽  
Full Size ◽  
Passive Safety Systems ◽  
Flow Phenomena ◽  
Water Reactors ◽  
Safety Systems ◽  
Principal Design

Scientific designs of two next-generation simplified boiling water reactors (SBWRs) namely, a compact modular 200 MWe SBWR and a full-size 1200-MWe SBWR have been developed. The design involved identification of principal design criteria dictated by the safe operation of the reactor, identification of coolant requirements, and the design of the engineered safety and emergency cooling systems based on passive systems. A detailed scaling analysis was performed. The results of the scaling study were used in the performance of the integral tests and data analysis. The scaling analysis identified key thermalhydraulics parameters that govern flow phenomena in SBWRs. The analysis was based on the three-level scaling approach.

Study of a Natural-Circulation Boiling Water Reactor with Passive Safety

1990 ◽  
Vol 92 (2) ◽  
pp. 260-268 ◽  
Author(s):  
Hideo Nagasaka ◽  
Takashi Sato ◽  
Hirohide Oikawa ◽  
Ryoichi Hamazaki ◽  
Kenji Arai ◽  
...  
Keyword(s):  
Natural Circulation ◽  
Boiling Water ◽  
Passive Safety ◽  
Boiling Water Reactor ◽  
Water Reactor
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