Preliminary design and front-end fuel cycle assessment of 200 MWt marine molten chloride fast reactor

• A preliminary design of a 200 MWt Marine Molten Chloride Fast Reactor (MMCFR) was developed. • Long-lived core design with Partial Fuel Change (PFC) mechanism. • Using Constant Replacement scheme in PFC mechanism lowers fuel consumption by 20%. • Reactivity swing is maintained below 5% throughout burnup using burnable absorber. • Control drum worth sufficient to shut down the reactor until end of cycle. The molten Chloride Fast Reactor (MCFR) emerges as one of the advanced nuclear reactor designs for use in a nuclear marine propulsion. This paper delineates the preliminary design of a 200 MWt Marine MCFR (MMCFR) intended as a propulsion for zero-carbon large container ship, focusing on the neutronic analysis and fuel cycle assessment. The MMCFR employs eutectic 66NaCl-34UCl 3 as the fuel with 19.55 wt% enriched uranium as the initial fuel contained in a BeO-reflected core, operated as a long-lived core and batchwise refuelling to simplify reactivity control and refuelling mechanism in a constrained space. As the MMCFR is designed with a compact core and large initial reactivity, the innovative Partial Fuel Change scheme is proposed to optimise fuel consumption and reduce the strain in the front-end fuel cycle, with Constant Mol or Constant Replacement scenario. Initial reactivity is suppressed using burnable absorber (BA) rods and control drums are used to control the reactivity and core shutdown. Neutronic and depletion calculations for the MMCFR design were performed using Serpent-2 code and ENDF/B-VII.0 library. The optimum front-end fuel cycle was obtained to be Constant Replacement scenario with lowest uranium consumption. Meanwhile, excess reactivity can be maintained below 5% throughout operational time by using BA and control drum, whilst temperature coefficient of reactivity (TCR) is sufficiently negative, ensuring the MMCFR fulfils the safety criteria.

Authors

Institutions

Publication Details

Journal
Annals of Nuclear Energy
Published
2026-01-08
DOI
https://doi.org/10.1016/j.anucene.2026.112124
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00
Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Preliminary design and front-end fuel cycle assessment of 200 MWt marine molten chloride fast reactor

Tomohiro Okamura, Masahiko Nakase, Kenji Nishihara, Andika Putra Dwijayanto
Annals of Nuclear Energy
Nuclear reactor physics and engineering
article

Preliminary design and front-end fuel cycle assessment of 200 MWt marine molten chloride fast reactor

Tomohiro Okamura, Masahiko Nakase, Kenji Nishihara, Andika Putra Dwijayanto
article en

Abstract

• A preliminary design of a 200 MWt Marine Molten Chloride Fast Reactor (MMCFR) was developed. • Long-lived core design with Partial Fuel Change (PFC) mechanism. • Using Constant Replacement scheme in PFC mechanism lowers fuel consumption by 20%. • Reactivity swing is maintained below 5% throughout burnup using burnable absorber. • Control drum worth sufficient to shut down the reactor until end of cycle. The molten Chloride Fast Reactor (MCFR) emerges as one of the advanced nuclear reactor designs for use in a nuclear marine propulsion. This paper delineates the preliminary design of a 200 MWt Marine MCFR (MMCFR) intended as a propulsion for zero-carbon large container ship, focusing on the neutronic analysis and fuel cycle assessment. The MMCFR employs eutectic 66NaCl-34UCl 3 as the fuel with 19.55 wt% enriched uranium as the initial fuel contained in a BeO-reflected core, operated as a long-lived core and batchwise refuelling to simplify reactivity control and refuelling mechanism in a constrained space. As the MMCFR is designed with a compact core and large initial reactivity, the innovative Partial Fuel Change scheme is proposed to optimise fuel consumption and reduce the strain in the front-end fuel cycle, with Constant Mol or Constant Replacement scenario. Initial reactivity is suppressed using burnable absorber (BA) rods and control drums are used to control the reactivity and core shutdown. Neutronic and depletion calculations for the MMCFR design were performed using Serpent-2 code and ENDF/B-VII.0 library. The optimum front-end fuel cycle was obtained to be Constant Replacement scenario with lowest uranium consumption. Meanwhile, excess reactivity can be maintained below 5% throughout operational time by using BA and control drum, whilst temperature coefficient of reactivity (TCR) is sufficiently negative, ensuring the MMCFR fulfils the safety criteria.

Annals of Nuclear EnergyVol. 229
Tokyo Institute of Technology (JP), Japan Atomic Energy Agency (JP)
Life below water
Openalex Percentile: Top 95%
Nuclear reactor physics and engineering
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.