Loss-of-Coolant-Accident and Anticipated Transient Without Scram Calculations for Homogeneous and Heterogeneous Advanced Pressurized Water Reactors

1988 ◽  
Vol 80 (1) ◽  
pp. 133-152 ◽  
Author(s):  
Mario Dalle Donne ◽  
Claudio Ferrero
Keyword(s):  
Pressurized Water Reactors ◽  
Pressurized Water ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Water Reactors

A Preliminary Safety Analysis of the Whole Assembly Seed-Blanket Heterogeneous PWR Core

2004 ◽  
Author(s):  
Jeongik Lee ◽  
Pradip Saha ◽  
Mujid S. Kazimi ◽  
Won-Jae Lee
Keyword(s):  
Temperature Rise ◽  
Safety Analysis ◽  
Complete Loss ◽  
Pressurized Water Reactors ◽  
Primary Flow ◽  
Pressurized Water ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Water Reactors ◽  
Safety Limit

The “Whole Assembly Seed and Blanket” (WASB) design, which utilizes mostly thorium in the blanket, consists of 84 seed and 109 blanket assemblies which may be backfitted into existing Pressurized Water Reactors (PWRs). Since the seed assemblies produce significantly more power than the blanket assemblies, a preliminary safety analysis of this design has been performed. Three accidents/transients (Large Break Loss of Coolant Accident (LBLOCA), Complete Loss of Primary Flow (LOPF) and Loss of Off-site Power (LOSP)), have been analyzed for both the WASB design and a typical all UO2 design for a typical 4-Loop Westinghouse PWR plant. LBLOCA results show that the peak cladding temperature (PCT) for the WASB design is approximately 260 K higher than that for a typical PWR design. However, this higher PCT for the WASB design is still about 200 K lower than the present regulatory safety limit. The response of the WASB and all UO2 core for LOPF and LOSP transients are very similar, and no post-DNB type rapid cladding temperature rise was observed in either of the two calculations.

Zinc corrosion after loss-of-coolant accidents in pressurized water reactors – Physicochemical effects

2014 ◽  
Vol 280 ◽  
pp. 570-578 ◽  
Author(s):  
Holger Kryk ◽  
Wolfgang Hoffmann ◽  
Wolfgang Kästner ◽  
Sören Alt ◽  
André Seeliger ◽  
...  
Keyword(s):  
Pressurized Water Reactors ◽  
Pressurized Water ◽  
Loss Of Coolant ◽  
Zinc Corrosion ◽  
Water Reactors

scholarly journals Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions

2020 ◽  
Author(s):  
Hongbin Zhang ◽  
Cole Blakely ◽  
Jianguo Yu
Keyword(s):  
Operating Time ◽  
Economic Benefits ◽  
Pressurized Water ◽  
Fuel Rod ◽  
Current Limit ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Water Reactors ◽  
Accident Conditions ◽  
Operating Cycles

Abstract Extending the fuel discharge burnup level, e.g., from the current limit of rod averaged discharge burnup limit of 62 GWD/MT to a proposed new limit of 75 GWD/MT, can provide significant economic benefits to the current fleet of operating light water reactors (LWRs). It allows for longer operating cycles and improved resource utilization. The major economic gain of longer operating cycles is attributable to the increased capacity factor resulting from decreased refueling time as a fraction of total operating time, as well as fewer assemblies to be discharged for a given amount of energy produced. The main licensing challenges for higher burnup fuel are to ensure fuel rod safety under design basis accident conditions, especially under large-break loss-of-coolant accident (LBLOCA) and reactivity insertion accident (RIA). In this work, two-year cycle core design for a typical 4-loop pressurized water reactor (PWR) is performed with enrichment increased up to 6% and burnup extended to 75 GWD/MT. The fuel rod burst potential evaluations under large-break loss-of-coolant accident (LBLOCA) conditions are subsequently performed using the multi-physics best estimate plus uncertainty analysis framework LOTUS (LOCA Toolkit for the U.S. LWRs) and the preliminary results are presented.

Zinc corrosion after loss-of-coolant accidents in pressurized water reactors – Thermo- and fluid-dynamic effects

2016 ◽  
Vol 305 ◽  
pp. 489-502 ◽  
Author(s):  
André Seeliger ◽  
Sören Alt ◽  
Wolfgang Kästner ◽  
Stefan Renger ◽  
Holger Kryk ◽  
...  
Keyword(s):  
Fluid Dynamic ◽  
Pressurized Water Reactors ◽  
Dynamic Effects ◽  
Pressurized Water ◽  
Loss Of Coolant ◽  
Zinc Corrosion ◽  
Water Reactors
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