Abstract
The results of the effect of various parameters on the reactivity void response of an advanced pressurized water reactor (APWR) containing mixed-oxide (plutonium and **2**3**8U) fuel are presented. The parameters studied include the moderator-to-fuel ratio; the presence of **2**3**8U and **2**4**0Pu in the fuel; the presence of parasitic (thermal) absorbers; the variation of eta of **2**3**9 Pu as a function of energy; the assumption that the water in the reactor core upon voiding remains uniform in density; the ratio of **2**3**9Pu/**2**4**1Pu atoms; and the treatment of neutrons in the resonance energy range. It is shown that using the WIMS-D code to determine neutron group constants at low levels of water loss ( less than 40%) from the core is usually adequate for APWR studies and is conservative over the entire range studied.
Original language | English |
---|---|
Pages (from-to) | 225-239 |
Number of pages | 15 |
Journal | Nuclear Technology |
Volume | 80 |
Issue number | 2 |
DOIs | |
State | Published - 1 Jan 1988 |
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Condensed Matter Physics