Core Design

  • Yoshiaki Oka
  • Seiichi Koshizuka
  • Yuki Ishiwatari
  • Akifumi Yamaji
Chapter

Abstract

This chapter presents the design concepts of the Super LWR core, including fuel rod and fuel assembly designs. The design concepts are comprehensively described with the design targets, criteria, margins, boundary conditions, and future requirements for further research and development. The design methods developed for the core designs are essentially equivalent to those methods adopted in designing commercial LWR cores. They include three-dimensional neutronic and thermal-hydraulic coupled core calculations, subchannel analyses, statistical design uncertainty evaluations based on a Monte Carlo sampling technique, and fuel rod behavior analyses. These analyses and the methods for developing the core concepts are described in detail. The evolutions of the core design concepts with new ideas and advances in the design methods are also described. The established core concept achieves an average core outlet temperature of 500°C at 25 MPa with a once-through direct cycle plant system.

Keywords

Fatigue Nickel Zirconium Convection Chromium 

Notes

Glossary

AFS

Auxiliary feedwater system

ATWS

Anticipated transients without scram

ALHGR

Average linear heat generation rate

BOC

Beginning of cycle

BOP

Balance of plant

BOL

Beginning of life

BWR

Boiling water reactor

CFD

Computational fluid dynamics

CHF

Critical heat flux

DNB

Departure from nucleate boiling

DNBR

Departure from nucleate boiling ratio

EOL

End of life

FR

Fast reactor

FBR

Fast breeder reactor

FCMI

Fuel cladding mechanical interaction

FPP

Fossil fired power plant

FP

Fission product

HTD

Heat transfer deterioration

LMFBR

Liquid metal fast breeder reactor

ITDP

Improved Thermal Design Procedure

LLLP

Low leakage loading pattern

LOCA

Loss of coolant accident

LWR

Light water reactor

MCST

Maximum cladding surface temperature

MCSTDP

Monte Carlo Statistical Thermal Design Procedure

MDHFR

Minimum deterioration heat flux ratio

MTDP

Optimized Monte Carlo Thermal Design Process

MGS

General Statistical Method

MLHGR

Maximum linear heat generation rate

ODS

Oxide dispersion strengthened

PCMI

Pellet-cladding mechanical interaction

PCI

Pellet cladding interaction

PIJ

Collision probability calculation module

PWR

Pressurized water reactor

RIA

Reactivity insertion accident

RPV

Reactor pressure vessel

RTDP

Revised Thermal Design Procedure

RSS

Root Sum Square

SCC

Stress corrosion cracking

STDP

Statistical thermal design procedure

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Copyright information

© Springer Science+Business Media, LLC 2010

Authors and Affiliations

  • Yoshiaki Oka
    • 1
  • Seiichi Koshizuka
    • 2
  • Yuki Ishiwatari
    • 3
  • Akifumi Yamaji
    • 4
  1. 1.Department of Nuclear Energy Graduate School of Advanced Science and EngineeringWaseda UniversityShinjuku-kuJapan
  2. 2.Department of Systems Innovation Graduate School of EngineeringUniversity of TokyoBunkyo-kuJapan
  3. 3.Department of Nuclear Engineering and Management Graduate School of EngineeringUniversity of TokyoBunkyo-kuJapan
  4. 4.Department of Nuclear Engineering and ManagementUniversity of TokyoBunkyo-kuJapan

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