Prediction of Neutronic and Kinetic Parameters of Ghana Research Reactor 1 (GHARR-1) after 19 Years of Operation Using Monte Carlo-N Particle (MCNP) Code

• 作者: Bright Madinka Mweetwa Cecil Odoi Edward Horga Kordzo Akaho Emmanuel Ampomah-Amoako
• 来源期刊: 核科学与技术国际期刊(英文)
• 学科: 医学
• 关键词: Delayed NEUTRON Fraction NEUTRON Generation Time MODERATOR REACTIVITY Coefficient Power Peaking Factor
• 年，卷（期）: 2018,（4）
• 页码范围: 160-175
• 页数: 16页
• 分类号: R73

摘要

The Ghana Research Reactor-1 (GHARR-1) core was modified with an addition of a 9.0 mm layer of beryllium to the top shim tray to compensate for reactivity loss due to fuel depletion after 19 years of operation. Neutronic and kinetic parameters have been predicted using Monte Carlo N-Particle Code version 5 (MCNP5) to determine whether they were within acceptable operating margins. Excess reactivity, control rod worth, moderator reactivity coefficient, delayed neutron fraction and neutron generation time have been predicted as 3.86, 6.98, −0.1218 mk/°C, 8.17507 × 10−3 Δk/k, and 8.147 × 10−5 s respectively. These parameters compared favorably with those provided in the initial Safety Analysis Report.