Three-dimensional core design of high temperature supercritical-pressure light water reactor with neutronic and thermal-hydraulic coupling

Akifumi Yamaji, Yoshiaki Oka, Seiichi Koshizuka

Research output: Contribution to journalArticlepeer-review

84 Citations (Scopus)

Abstract

The equilibrium core of the High Temperature Supercritical-Pressure Light Water Reactor (SCLWR-H) is designed by three-dimensional neutronic and thermal-hydraulic coupled core calculations. The average coolant core outlet temperature of 500°C is accurately evaluated for the first time in the development of the SCLWR-H. The average coolant core outlet temperature is one of the key parameters, which must be accurately determined in order to establish the concept of this unique reactor design. However, it can only be determined by three-dimensional core design method, taking into account the control rod patterns, fuel loading patterns, coupling of the neutronic and thermal-hydraulic calculations, and burnup distribution of each fuel assembly. The R—Z two-dimensional core design method used in previous studies could not model or evaluate such parameters with sufficient accuracy. In this study, a three-dimensional equilibrium core design method for the SCLWR-H is established. This method can accurately evaluate the average coolant core outlet temperature and has permitted a comprehensive equilibrium core to be developed, which satisfies all design criteria. The design criteria are maximum fuel rod cladding surface temperature of 650°C, maximum linear heat generation rate of 39 kW/m, and a positive water density reactivity coefficient.

Original languageEnglish
Pages (from-to)8-19
Number of pages12
JournalJournal of Nuclear Science and Technology
Volume42
Issue number1
DOIs
Publication statusPublished - 2005 Jan
Externally publishedYes

Keywords

  • Average coolant core outlet temperature
  • Equilibrium core
  • Generation IV reactor
  • Light water cooling
  • Neutronic and thermal-hydraulic coupling
  • Once-through direct cycle
  • Supercritical-pressure
  • Thermal reactor
  • Three-dimensional core calculations

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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