Lattice parameter measurements on cluster-type fuel for advanced thermal reactor.
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概要
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The behavior of neutrons in a highly heterogeneous unit cell consisting of D<SUB>2</SUB>O moderator, H<SUB>2</SUB>O coolant and a 28-pin fuel cluster contained in a pressure tube has been studied through lattice parameter measurements covering three different <SUP>232</SUP>U enrichments, four coolant void fractions and two lattice pitches. A single-region core configuration was adopted, with which measurements were made to determine-in relation to coolant void fraction-the critical D<SUB>2</SUB>O level, as well as various lattice parameters.<BR>A strong dependence on coolant void was observed for the critical level and the lattice parameters, in the case of the smaller 22.5 cm pitch lattice, due to the positive effect on core reactivity exerted by the slowing-down faculty of H<SUB>2</SUB>O in the epithermal energy region. With the larger 25.0 cm pitch, however, no meaningful dependence on void fraction was shown by any of the measured values, and this was ascribed to a compensating negative effect due to enhanced thermal neutron self-shielding in the fuel region produced by the H<SUB>2</SUB>O coolant.<BR>The results of cell calculations obtained by means of the METHUSELAH-II code showed generally good agreement with experimentally determined data, for both critical D<SUB>2</SUB>0 levels and lattice parameters, in the case of coolant-filled lattices (0, 30 and 70% void fractions). For lattices devoid of coolant (100% void fraction), however, discrepancies in lattice parameters-particularly in ρ<SUP>28</SUP>-produced corresponding deviations in core reactivity amounting to 1% in excess of those incurred with other void fractions.
- 一般社団法人 日本原子力学会の論文
著者
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SAKATA Hajime
Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation
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SAKATA Hajime
Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corp.
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HACHIYA Yuuki
Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corp.
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FUKUMURA Nobuo
Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation
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NISHI Akito
Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation
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IIJIMA Kazuyoshi
Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation
関連論文
- Fuel temperature coefficients of reactivity for heavy-water-moderated, cluster-type fuel lattices.
- Lattice parameter measurements on cluster-type fuel for advanced thermal reactor.