Peacock: A Monte Carlo Code for Reactor Physics

Peacock is the newest reactor physics software developed by Studsvik Scandpower Inc. (SSP). Peacock is a continuous-energy, general geometry, Monte Carlo neutron transport code system designed especially for reactor physics calculations. This development represents a commitment to modern software development and best-practices at SSP. The quality assurance program for Peacock is particularly noteworthy as it implements the American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance-1 (NQA-1) program, includes 10 CFR Part 21 reporting, and has dedicated staff to support users. Notable capabilities of Peacock are detailed herein, including the depletion methodology and temperature interpolation of fundamental nuclear data. These capabilities are demonstrated in a series of calculations including a Boiling Water Reactor (BWR) control cell and a Sodium-cooled Fast Reactor (SFR) lattice.

Authors

Publication Details

Journal
Nuclear Science and Engineering
Published
2026-10-26
DOI
https://doi.org/10.1080/00295639.2026.2746851
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00
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Peacock: A Monte Carlo Code for Reactor Physics

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Peacock: A Monte Carlo Code for Reactor Physics

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article en

Abstract

Peacock is the newest reactor physics software developed by Studsvik Scandpower Inc. (SSP). Peacock is a continuous-energy, general geometry, Monte Carlo neutron transport code system designed especially for reactor physics calculations. This development represents a commitment to modern software development and best-practices at SSP. The quality assurance program for Peacock is particularly noteworthy as it implements the American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance-1 (NQA-1) program, includes 10 CFR Part 21 reporting, and has dedicated staff to support users. Notable capabilities of Peacock are detailed herein, including the depletion methodology and temperature interpolation of fundamental nuclear data. These capabilities are demonstrated in a series of calculations including a Boiling Water Reactor (BWR) control cell and a Sodium-cooled Fast Reactor (SFR) lattice.

Nuclear Science and Engineering
Openalex Percentile: Top 18%
Nuclear reactor physics and engineering
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