0
Research Papers

Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle

[+] Author and Article Information

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada

Leslie Kicka

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada
e-mail: leslie.kicka@uoit.net

Subhramanyu Mohapatra

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada
e-mail: Subhramanyu.Mohapatra@uoit.ca

Eleodor Nichita

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada
e-mail: Eleodor.Nichita@uoit.ca

Peter Schwanke

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada
e-mail: Peter.Schwanke@uoit.ca

Manuscript received January 28, 2016; final manuscript received August 15, 2016; published online December 20, 2016. Assoc. Editor: Michal Kostal.

ASME J of Nuclear Rad Sci 3(1), 011011 (Dec 20, 2016) (5 pages) Paper No: NERS-16-1008; doi: 10.1115/1.4034571 History: Received January 28, 2016; Accepted August 15, 2016

Abstract

Deterministic and Monte Carlo methods are regularly employed to conduct lattice calculations. Monte Carlo methods can effectively model a large range of complex geometries and, compared to deterministic methods, they have the major advantage of reducing systematic errors and are computationally effective when integral quantities such as effective multiplication factor or reactivity are calculated. In contrast, deterministic methods do introduce discretization approximations but usually require shorter computation times than Monte Carlo methods when detailed flux and reaction-rate solutions are sought. This work compares the results of the deterministic code DRAGON to the Monte Carlo code Serpent in the calculation of the reactivity effects for a pressurized heavy water reactor (PHWR) lattice cell containing a 37-element, natural uranium fuel bundle with heavy water coolant and moderator. The reactivity effects are determined for changes to the coolant, moderator, and fuel temperatures and to the coolant and moderator densities for zero-burnup, mid-burnup [$3750 MWd/t(U)$] and discharge burnup [$7500 MWd/t(U)$] fuel. It is found that the overall trend in the reactivity effects calculated using DRAGON match those calculated using Serpent for the burnup cases considered. However, differences that exceed the amount attributable to statistical error have been found for some reactivity effects, particularly for perturbations to coolant and moderator density and fuel temperature.

<>

Figures

Fig. 1

PHWR lattice cell

Fig. 2

Discretized DRAGON model of the PHWR lattice cell

Fig. 3

Discretized Serpent model of the PHWR lattice cell

Fig. 4

Fuel temperature reactivity effect

Fig. 5

Coolant temperature reactivity effect

Fig. 6

Moderator temperature reactivity effect

Fig. 7

Coolant density reactivity effect

Fig. 8

Moderator density reactivity effect

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related Proceedings Articles
Related eBook Content
Topic Collections

• TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
• EMAIL: asmedigitalcollection@asme.org