Results of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel tests in a bor-60 reactor to burnup 12% h.a
The results of post-reactor studies of U 0.55 Pu 0.45 N and U 0.4 Pu 0.6 N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 4...
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| Published in: | Atomic energy (New York, N.Y.) Vol. 110; no. 6; pp. 412 - 429 |
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| Main Authors: | , , , , , , , , |
| Format: | Journal Article |
| Language: | English |
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01-10-2011
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| Abstract | The results of post-reactor studies of U
0.55
Pu
0.45
N and U
0.4
Pu
0.6
N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 430 and 540 W/cm. All fuel elements remained hermetic; the ChS-68 steel cladding (20% cold deformation) retained excess plasticity. The maximum zone of interaction between the cladding and the fuel and fission products did not exceed 15 μm. The swelling rate of U
0.4
Pu
0.6
N and U
0.55
Pu
0.45
N fuel was 1.1 and 0.68%/% burnup, respectively. The gas release did not exceed 19.3 and 19%. The steel damage dose was 43 dpa. The character of the porosity distribution in the fuel affects the swelling and gas release. |
|---|---|
| AbstractList | The results of post-reactor studies of U
0.55
Pu
0.45
N and U
0.4
Pu
0.6
N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 430 and 540 W/cm. All fuel elements remained hermetic; the ChS-68 steel cladding (20% cold deformation) retained excess plasticity. The maximum zone of interaction between the cladding and the fuel and fission products did not exceed 15 μm. The swelling rate of U
0.4
Pu
0.6
N and U
0.55
Pu
0.45
N fuel was 1.1 and 0.68%/% burnup, respectively. The gas release did not exceed 19.3 and 19%. The steel damage dose was 43 dpa. The character of the porosity distribution in the fuel affects the swelling and gas release. |
| Author | Shishkov, M. G. Kryukov, F. N. Rogozkin, B. D. Nikitin, O. N. Zabudko, L. M. Fedorov, Yu. E. Kuzmin, S. V. Belyaeva, A. V. Stepennova, N. M. |
| Author_xml | – sequence: 1 givenname: B. D. surname: Rogozkin fullname: Rogozkin, B. D. organization: Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM) – sequence: 2 givenname: N. M. surname: Stepennova fullname: Stepennova, N. M. organization: Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM) – sequence: 3 givenname: Yu. E. surname: Fedorov fullname: Fedorov, Yu. E. organization: Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM) – sequence: 4 givenname: M. G. surname: Shishkov fullname: Shishkov, M. G. organization: Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM) – sequence: 5 givenname: F. N. surname: Kryukov fullname: Kryukov, F. N. organization: State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR) – sequence: 6 givenname: S. V. surname: Kuzmin fullname: Kuzmin, S. V. organization: State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR) – sequence: 7 givenname: O. N. surname: Nikitin fullname: Nikitin, O. N. organization: State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR) – sequence: 8 givenname: A. V. surname: Belyaeva fullname: Belyaeva, A. V. organization: State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR) – sequence: 9 givenname: L. M. surname: Zabudko fullname: Zabudko, L. M. organization: State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI) |
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| CitedBy_id | crossref_primary_10_1007_s10512_016_0168_x crossref_primary_10_1016_j_jnucmat_2023_154330 crossref_primary_10_31089_1026_9428_2021_61_9_558_566 crossref_primary_10_1007_s10512_014_9893_1 crossref_primary_10_1016_j_anucene_2019_106963 crossref_primary_10_1016_j_jnucmat_2023_154852 crossref_primary_10_1088_1742_6596_891_1_012184 crossref_primary_10_1016_j_jnucmat_2022_153803 crossref_primary_10_1007_s10512_013_9704_0 crossref_primary_10_1007_s10512_017_0254_8 crossref_primary_10_1007_s10512_012_9576_8 crossref_primary_10_1021_acs_jpcc_1c08523 crossref_primary_10_1007_s10512_015_9952_2 crossref_primary_10_3897_nucet_9_111914 |
| Cites_doi | 10.1016/j.jnucmat.2004.01.002 10.3327/jnst.30.824 10.1023/B:ATEN.0000018996.79185.bc |
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| Keywords | Fuel Element Fuel Kernel Fuel Assembly Plutonium Fission Product |
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| References | CR2 CR4 CR3 CR6 CR5 CR8 CR19 CR7 CR18 Rogozkin, Stepennova, Bergman, Proshkin (CR10) 2003; 95 CR17 CR9 CR16 CR15 CR14 Orlov, Gromov, Adamov (CR1) 1992; 72 CR13 CR11 Arai, Suzuki, Iwai (CR12) 1993; 30 Tanaka, Maeda, Katsuyama (CR20) 2004; 327 Y Arai (9442_CR12) 1993; 30 VV Orlov (9442_CR1) 1992; 72 9442_CR9 9442_CR8 9442_CR7 9442_CR6 9442_CR5 9442_CR4 9442_CR16 9442_CR3 9442_CR17 9442_CR2 9442_CR14 9442_CR15 BD Rogozkin (9442_CR10) 2003; 95 9442_CR18 K Tanaka (9442_CR20) 2004; 327 9442_CR19 9442_CR13 9442_CR11 |
| References_xml | – volume: 72 start-page: 317 issue: 4 year: 1992 end-page: 323 ident: CR1 article-title: Unconventional concepts of inherently safe nuclear power plants publication-title: At. Énerg. contributor: fullname: Adamov – volume: 327 start-page: 77 year: 2004 end-page: 87 ident: CR20 article-title: Fission gas release and swelling in uranium-plutonium mixed nitride fuels publication-title: J. Nucl. Mater. doi: 10.1016/j.jnucmat.2004.01.002 contributor: fullname: Katsuyama – ident: CR19 – ident: CR18 – ident: CR3 – ident: CR4 – ident: CR14 – ident: CR15 – ident: CR2 – ident: CR16 – ident: CR17 – volume: 30 start-page: 824 issue: 8 year: 1993 end-page: 830 ident: CR12 article-title: Fabrication of uranium-plutonium mixed nitride fuel pins for irradiation tests in JMTR publication-title: Nucl. Sci. Techn. doi: 10.3327/jnst.30.824 contributor: fullname: Iwai – ident: CR13 – ident: CR11 – ident: CR9 – volume: 95 start-page: 428 issue: 6 year: 2003 end-page: 438 ident: CR10 article-title: Thermochemical stability, radiation tests, fabrication, and regeneration of mononitride fuel publication-title: At. Énerg. contributor: fullname: Proshkin – ident: CR6 – ident: CR5 – ident: CR7 – ident: CR8 – ident: 9442_CR17 – ident: 9442_CR16 – ident: 9442_CR18 – ident: 9442_CR19 – ident: 9442_CR14 – ident: 9442_CR15 – ident: 9442_CR13 – ident: 9442_CR4 – ident: 9442_CR9 – volume: 95 start-page: 428 issue: 6 year: 2003 ident: 9442_CR10 publication-title: At. Énerg. doi: 10.1023/B:ATEN.0000018996.79185.bc contributor: fullname: BD Rogozkin – ident: 9442_CR3 – ident: 9442_CR5 – ident: 9442_CR8 – ident: 9442_CR6 – ident: 9442_CR7 – ident: 9442_CR2 – volume: 30 start-page: 824 issue: 8 year: 1993 ident: 9442_CR12 publication-title: Nucl. Sci. Techn. doi: 10.3327/jnst.30.824 contributor: fullname: Y Arai – volume: 72 start-page: 317 issue: 4 year: 1992 ident: 9442_CR1 publication-title: At. Énerg. contributor: fullname: VV Orlov – ident: 9442_CR11 – volume: 327 start-page: 77 year: 2004 ident: 9442_CR20 publication-title: J. Nucl. Mater. doi: 10.1016/j.jnucmat.2004.01.002 contributor: fullname: K Tanaka |
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| Snippet | The results of post-reactor studies of U
0.55
Pu
0.45
N and U
0.4
Pu
0.6
N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium... |
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| SubjectTerms | Hadrons Heavy Ions Nuclear Chemistry Nuclear Energy Nuclear Physics Physics Physics and Astronomy |
| Title | Results of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel tests in a bor-60 reactor to burnup 12% h.a |
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