Published 2005 | Version v1
Computer medium

Comparative study on plutonium and MA recycling in equilibrium burnup and standard burnup of PWR

  • 1. Dept. of Physics, Bandung Institute of Technology, Bandung (Indonesia)
  • 2. Tokyo Inst. of Technology, Dept. of Nuclear Engineering, Tokyo (JP)

Description

The equilibrium burnup model is a powerful method since its can handle all possible generated nuclides in any nuclear system. Moreover, this method is a simple time independent method. Hence the equilibrium burnup method could be very useful for evaluating and forecasting the characteristics of any nuclear fuel cycle, even the strange one, e.g. all nuclides are confined in the reactor. However, this method needs to be verified since the method is not a standard tool. The present study aimed to compare the characteristics of plutonium recycling and plutonium and minor actinides (MA) recycling in PWR with the equilibrium burnup and the standard burnup. In order to become more comprehensive study, an influence of moderator-to-fuel volume ratio (MFR) changes by changing the pin-pitch of fuel cell has been evaluated. The MFR ranges from 0.5 to 4.0. For the equilibrium burnup we used equilibrium cell-burnup code. We have employed 1368 nuclides in the equilibrium calculation with 129 of them are heavy metals (HMs). For standard burnup, SRAC2002 code has been utilized with 26 HMs and 66 fission products (FPs). The JENDL 3.2 library has been employed for both burnup schemes. The uranium, plutonium and MA vector, which resulted from the equilibrium burnup are directly used as fuel input composition for the standard burnup calculation. Both burnup results demonstrate that plutonium recycling and plutonium and MA recycling can be conducted safer in tight lattice core. They are also show the similar trend in neutron spectrum, which become harder with the increasing number of recycled heavy nuclides as well as the decreasing of the MFR values. However, there are some discrepancy on the effective multiplication factor and the conversion ratio, especially for the reactor core for MFR ≥ 2.0. (author)

Part of:
GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability
Imprint Pagination
[2562 p.]
Journal Page Range
[4 p.]

Conference

Title
International conference on nuclear energy systems for future generation and global sustainability
Acronym
GLOBAL 2005
Dates
9-13 Oct 2005
Place
Tsukuba, Ibaraki (Japan)

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name GL5XX, Paper ID GL505DF.pdf; 10 refs., 4 figs., 2 tabs.