軽水炉溶融燃料取り出し方策およびその際の臨界安全管理 (9) - 各種中性子吸収材の試作・評価 (Measures to remove the LWR core debris and its criticality safety evaluation (9) - manufacturing and evaluation of the neutron absorbing materials)

Submitted by Fukushima Nucl… on Fri, 12/04/2020 - 10:12

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Media Creator Username

日本原子力研究開発機構

Media Creator Realname

日本原子力研究開発機構

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Scope

One Page

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Language

Japanese

Media Date Create

Sun, 03/30/2014 - 16:00

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Japanese Title

軽水炉溶融燃料取り出し方策およびその際の臨界安全管理 (9) - 各種中性子吸収材の試作・評価

Japanese Description

軽水炉溶融燃料取り出し方策およびその際の臨界安全管理 (9) - 各種中性子吸収材の試作・評価

English Title

Measures to remove the LWR core debris and its criticality safety evaluation (9) - manufacturing and evaluation of the neutron absorbing materials

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https://f-archive.jaea.go.jp/dspace/handle/faa/41750

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https://f-archive.jaea.go.jp/dspace/handle/faa/41750