Published November 2001
| Version v1
Journal article
Preliminary study of the tight lattice pressured heavy water reactor loaded with Pu/U and Th/U mixed fuels
Creators
- 1. Nuclear Science Department, Research Reactor Institute, Kyoto University, Osaka (Japan)
Description
To improve nuclear fuel utilization efficiency and prolong fuel cycle burn-up, a tight pitch lattice pressured heavy water reactor was investigated as an alternative of next generation of power reactors. It is shown that the high conversion ratio and negative coolant void reactivity coefficient are challenges in the reactor core physics designs. Various techniques were proposed to solve these problems. A tight pitch lattice and mixed fuel assemblies pressure heavy water reactor concept was investigated. By utilizing numerical simulation technique, it is demonstrated that reactor core mixed with Pu/U and Th/U assemblies can achieve high conversion ratio (0.98), long burn-up (60 GWD/t) and negative void reactivity coefficients
Additional details
Publishing Information
- Journal Title
- Nuclear Science and Techniques
- Journal Volume
- 12
- Journal Issue
- 4
- Journal Page Range
- p. 302-308
- ISSN
- 1001-8042
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 33024876
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BURNUP; CONVERSION RATIO; COOLANTS; FUEL ASSEMBLIES; HEAVY WATER COOLED REACTORS; MIXING; NUCLEAR FUELS; NUMERICAL SOLUTION; PLUTONIUM; PWR TYPE REACTORS; REACTOR LATTICE PARAMETERS; THORIUM; URANIUM; VOID COEFFICIENT
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; METALS; POWER REACTORS; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS