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Volumn 228, Issue 1-3, 2004, Pages 21-34

Characterization of neutron field in the experimental fast reactor JOYO for fuel and structural material irradiation test

Author keywords

[No Author keywords available]

Indexed keywords

BUILDING MATERIALS; COOLANTS; CREEP; DIFFUSION; DOSIMETRY; ERROR ANALYSIS; HELIUM; MATHEMATICAL MODELS; NEUTRON IRRADIATION; SPECTRUM ANALYSIS; SPENT FUELS; URANIUM;

EID: 0442296262     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.06.003     Document Type: Conference Paper
Times cited : (24)

References (20)
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    • (1994) Annual Book of ASTM Standards
  • 2
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    • Standard practice for characterizing neutron exposures in iron and low alloy steels in terms of displacement per atom (dpa)
    • vol. 12.02
    • ASTM, 2001. Standard practice for characterizing neutron exposures in iron and low alloy steels in terms of displacement per atom (dpa). In: Annual Book of ASTM Standards, vol. 12.02, E693-01.
    • (2001) Annual Book of ASTM Standards
  • 4
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    • Shielding design study of the demonstration fast breeder reactor (1) - Evaluation of the JASPER experiment and its analysis results
    • Tsukuba, Japan, October 17-22, 1999
    • Handa, H., et al., 2000. Shielding design study of the demonstration fast breeder reactor (1) - evaluation of the JASPER experiment and its analysis results. In: Proceedings of the Ninth International Conference on Radiation Shielding, Tsukuba, Japan, October 17-22, 1999, p. 110.
    • (2000) Proceedings of the Ninth International Conference on Radiation Shielding , pp. 110
    • Handa, H.1
  • 6
    • 0442273605 scopus 로고    scopus 로고
    • Development of helium accumulation fluence monitor for fast reactor dosimetry
    • ENS/ASTM, Brussels, August 18-23
    • Ito, C., et al., 2002. Development of helium accumulation fluence monitor for fast reactor dosimetry. In: Proceedings of the 11th International Symposium on Reactor Dosimetry, ENS/ASTM, Brussels, August 18-23, pp. 150-159.
    • (2002) Proceedings of the 11th International Symposium on Reactor Dosimetry , pp. 150-159
    • Ito, C.1
  • 10
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    • Japanese evaluated nuclear data library version 3 revision-2: JENDL-3.2
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    • (1995) J. Nucl. Sci. Technol. , vol.32 , Issue.12 , pp. 1259
    • Nakagawa, T.1    Shibata, K.2
  • 11
    • 0442305051 scopus 로고    scopus 로고
    • JOYO MK-II core characteristics database
    • Japan, November 21-22
    • Ohkawachi, Y., et al., 2002. JOYO MK-II core characteristics database. In: Proceedings of the 2002 Symposium on Nuclear Data, Japan, November 21-22, pp. 294-299.
    • (2002) Proceedings of the 2002 Symposium on Nuclear Data , pp. 294-299
    • Ohkawachi, Y.1
  • 14
    • 0442289182 scopus 로고
    • Dosimetry test program on experimental fast reactor JOYO
    • Sasaki M., Suzuki S. Dosimetry test program on experimental fast reactor JOYO. PNC Tech. Rev. 38:1981;72-96.
    • (1981) PNC Tech. Rev. , vol.38 , pp. 72-96
    • Sasaki, M.1    Suzuki, S.2
  • 15
    • 45149089086 scopus 로고    scopus 로고
    • Fission rate analysis of fast reactor fuel performance test using MCNP
    • Lisbon, October 23-26
    • Sekine, T., Aoyama, T., 2001. Fission rate analysis of fast reactor fuel performance test using MCNP. In: Proceedings of MC2000, Lisbon, October 23-26, pp. 737-742.
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  • 16
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  • 18
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  • 19
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