Abstract
The computer code CLUB has been developed to calculate lattice parameters as a function of burnup for a pressurised heavy water reactor (PHWR) lattice cell containing fuel in the form of cluster. It solves the multigroup integral transport equation by the method based on combination of small scale collision probability (CP) method and large scale interface current technique. The calculations are performed by using WIMS 69 group cross section library or its condensed versions of 27 or 28 group libraries. It can also compute Keff from the given geometrical buckling in the input using multigroup diffusion theory in fundamental mode. The first order differential burnup equations can be solved by either Trapezoidal rule or Runge-Kutta method. (author). 17 refs., 2 figs.
Krishnani, P D
[1]
- Bhabha Atomic Research Centre, Bombay (India). Theoretical Physics Div.
Citation Formats
Krishnani, P D.
CLUB - a multigroup integral transport theory code for lattice calculations of PHWR cells.
India: N. p.,
1992.
Web.
Krishnani, P D.
CLUB - a multigroup integral transport theory code for lattice calculations of PHWR cells.
India.
Krishnani, P D.
1992.
"CLUB - a multigroup integral transport theory code for lattice calculations of PHWR cells."
India.
@misc{etde_10129524,
title = {CLUB - a multigroup integral transport theory code for lattice calculations of PHWR cells}
author = {Krishnani, P D}
abstractNote = {The computer code CLUB has been developed to calculate lattice parameters as a function of burnup for a pressurised heavy water reactor (PHWR) lattice cell containing fuel in the form of cluster. It solves the multigroup integral transport equation by the method based on combination of small scale collision probability (CP) method and large scale interface current technique. The calculations are performed by using WIMS 69 group cross section library or its condensed versions of 27 or 28 group libraries. It can also compute Keff from the given geometrical buckling in the input using multigroup diffusion theory in fundamental mode. The first order differential burnup equations can be solved by either Trapezoidal rule or Runge-Kutta method. (author). 17 refs., 2 figs.}
place = {India}
year = {1992}
month = {Dec}
}
title = {CLUB - a multigroup integral transport theory code for lattice calculations of PHWR cells}
author = {Krishnani, P D}
abstractNote = {The computer code CLUB has been developed to calculate lattice parameters as a function of burnup for a pressurised heavy water reactor (PHWR) lattice cell containing fuel in the form of cluster. It solves the multigroup integral transport equation by the method based on combination of small scale collision probability (CP) method and large scale interface current technique. The calculations are performed by using WIMS 69 group cross section library or its condensed versions of 27 or 28 group libraries. It can also compute Keff from the given geometrical buckling in the input using multigroup diffusion theory in fundamental mode. The first order differential burnup equations can be solved by either Trapezoidal rule or Runge-Kutta method. (author). 17 refs., 2 figs.}
place = {India}
year = {1992}
month = {Dec}
}