Published 2007 | Version v1
Miscellaneous

Safety characteristics of the super LWR design concept

  • 1. Tokyo Univ., Nuclear Professional School (Japan)
  • 2. Tokyo Univ., Dept. of Quantum Engineering and System Science (Japan)
  • 3. Tokyo Univ., Dept. of Nuclear Engineering and Management (Japan)

Description

The supercritical water cooled reactor (SCWR) is recognized as one of the Generation IV reactor concepts. The Super LWR is a thermal reactor version of the SCWR that is now being promoted and developed at the University of Tokyo. This paper describes safety design principle and a series of safety analyses for Super LWR to present the safety characteristics of this reactor concept. Safety of the Super LWR is characterized by the design features such as a once-through cooling system, supercritical-pressure operation and a coolant flow scheme with downward-flow water rods. The safety characteristics are investigated with the analyses of abnormal transients, accidents and anticipated transient without scram (ATWS). The good safety performance of the Super LWR well appears under ATWS conditions. Besides the above good responses against loss-of-flow and pressurization, the Super LWR has self-controllability of the reactor power against flow abnormalities and reactivity insertion due to the coolant density and Doppler feedbacks. All the ATWS events satisfy the same criteria as those of the accidents with margin and settle to a high-temperature stable condition without any alternative action even for a high rating core. It is an outstanding safety advantage of the Super LWR

Availability note (English)

Available from: SFEN, 5 rue des Morillons, 75015 Paris (France)

Additional details

Publishing Information

Imprint Pagination
14 p.
Report number
INIS-FR--08-0667

Conference

Title
ICAPP 2007 - International congress on advances in nuclear power plants. The nuclear renaissance at work
Dates
13-18 May 2007
Place
Nice Acropolis (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
39069969
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ATWS; COMPUTERIZED SIMULATION; DEPRESSURIZATION; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; S CODES; SAFETY ANALYSIS; SPECIFICATIONS; SUPERCRITICAL STATE; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DESIGN BASIS ACCIDENTS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION

Optional Information

Notes
16 refs.