14–15 Nov 2024
熊取交流センター すまいるズ 煉瓦館
Asia/Tokyo timezone

Importance and issues of CaH2 TLS data for reactivity coefficient and core characteristics of MoveluXTM /超小型炉MoveluXTMにおけるCaH2の温度反応度特性と炉心特性における熱中性子散乱則データの重要性と課題

14 Nov 2024, 14:20
30m
熊取交流センター すまいるズ 煉瓦館

熊取交流センター すまいるズ 煉瓦館

大阪府泉南郡熊取町五門西1丁目10番1号

Speaker

Rei/礼 Kimura/木村 (Toshiba Energy Systems & Solutions Corporation/東芝エネルギーシステムズ株式会社)

Description

To realize a decarbonized society, various organizations are developing small modular reactors and micro-reactors [1]. Toshiba Energy Systems & Solutions has been developing a MoveluXTM reactor system with 10 MWt and 3-4 MWe power output. The MoveluXTM core uses less than 5% LEU as the nuclear fuel. Furthermore, calcium hydride (CaH2) is also used as the solid-state neutron moderator. The hydrogen in CaH2 dissociated above 800 C; thus, this temperature is the operation limitation temperature of the core. From the viewpoint of the core characteristics, the CaH2 moderator shows a positive temperature reactivity coefficient from room temperature to near the operation temperature [2].

The MoveluXTM core utilizes this positive temperature reactivity coefficient to assure critical safety during transport [3]. To evaluate this core characteristic, the TSL of CaH2 is very important input data for the core calculation. However, only JEFF published TSL data on the CaH2, and it was based on one experiment’s data.

On the other hand, the Toshiba Energy Systems & Solutions Corporation measured TSL of CaH2 in the past research with Tokyo Tech and Kyoto University. Additionally, JAEA also evaluates this TSL based on the simulation. The MoveluXTM core had around 200 pcm between these TLS data, furthermore, more than a 2% difference in temperature reactivity coefficient was confirmed. These differences were not small, thus, improvement of the CaH2 TSL data will be required.

References
[1] J. Buongiorno, et al, “The Future of Nuclear Energy in a Carbon-Constrained World”, Massachusetts Institute of Technology, MA, USA, (2018) p. 26.
[2] R. Kimura, S. Wada, “Temperature Reactivity Control of Calcium–Hydride–Moderated Small Reactor Core with Poison Nuclides”, Nucl. Sci. Eng., 193 (9), (2019) pp.1013-1022.
[3] R. Kimura, K. Asano, “Ensuring Criticality Safety of vSMR Core During Transport Based on Its Temperature Reactivity”, Nucl. Sci. Eng.,194 (3), (2020), pp.213-220.

Primary author

Rei/礼 Kimura/木村 (Toshiba Energy Systems & Solutions Corporation/東芝エネルギーシステムズ株式会社)

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