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Volumn 96, Issue 5, 2004, Pages 345-351

Supercritical-pressure water nuclear reactors

Author keywords

[No Author keywords available]

Indexed keywords

FUEL BREEDING; NEUTRON SPECTRUM; SUPERCRITICAL PRESSURE; WATER DENSITY;

EID: 4344674076     PISSN: 10634258     EISSN: None     Source Type: Journal    
DOI: 10.1023/B:ATEN.0000038101.90666.da     Document Type: Article
Times cited : (21)

References (9)
  • 1
    • 0035551005 scopus 로고    scopus 로고
    • Switching to supercritical parameters - A way to improve nuclear power plants with water-cooled reactors
    • P. L. Kirillov, "Switching to supercritical parameters - a way to improve nuclear power plants with water-cooled reactors," Teploénergetika, No. 12, 6-10 (2001).
    • (2001) Teploénergetika , Issue.12 , pp. 6-10
    • Kirillov, P.L.1
  • 2
    • 3543073227 scopus 로고    scopus 로고
    • Supercritical parameters - Future water-cooled reactors and nuclear power plants
    • P. L. Kirillov, "Supercritical parameters - future water-cooled reactors and nuclear power plants," At. Tekh. Rubezh., No. 6, 3-8 (2001).
    • (2001) At. Tekh. Rubezh. , Issue.6 , pp. 3-8
    • Kirillov, P.L.1
  • 3
    • 0036409882 scopus 로고    scopus 로고
    • Power generating units with VVÉR reactors with transcritical coolant parameters
    • V. V. Dolgov, "Power generating units with VVÉR reactors with transcritical coolant parameters," At. Énerg., 92, No. 4, 277-280 (2002).
    • (2002) At. Énerg. , vol.92 , Issue.4 , pp. 277-280
    • Dolgov, V.V.1
  • 4
    • 4344573019 scopus 로고
    • Development of power reactors such as the reactor at the Belyi Yar nuclear power plant with nuclear-superheated steam
    • N. A. Dollezhal', I. Ya. Emel'yanov, P. I. Aleshchenkov, et al., "Development of power reactors such as the reactor at the Belyi Yar nuclear power plant with nuclear-superheated steam," Report No. 309 at the 3rd Geneva Conference (1964).
    • (1964) Report No. 309 at the 3rd Geneva Conference , vol.309
    • Dollezhal, N.A.1    Emel'yanov, I.Ya.2    Aleshchenkov, P.I.3
  • 5
    • 4344576865 scopus 로고
    • Power-generating units with nuclear reactors with subcritical and supercritical steam parameters for operating in the half-peak load range of the power systems
    • Collection of Soviet Reports at the 20th Anniversay of Nuclear Power, Obninsk, June 25-27
    • P. I. Aleshchenkov, A. V. Bakanov, and G. A. Zvereva, "Power-generating units with nuclear reactors with subcritical and supercritical steam parameters for operating in the half-peak load range of the power systems," in: Experience in Operating Nuclear Power Plants and Paths for Further Development of Nuclear Power, Collection of Soviet Reports at the 20th Anniversay of Nuclear Power, Obninsk, June 25-27, 1974, Vol. 2, pp. 99-109.
    • (1974) Experience in Operating Nuclear Power Plants and Paths for further Development of Nuclear Power , vol.2 , pp. 99-109
    • Aleshchenkov, P.I.1    Bakanov, A.V.2    Zvereva, G.A.3
  • 6
    • 84862412189 scopus 로고    scopus 로고
    • On calculations of heat transfer in pipes and rod bundles with water flow at supercritical pressure
    • V. A. Grabezhnaya and P. L. Kirillov, "On calculations of heat transfer in pipes and rod bundles with water flow at supercritical pressure," Review FÉI-0297 (2003).
    • (2003) Review FÉI-0297
    • Grabezhnaya, V.A.1    Kirillov, P.L.2
  • 9
    • 84862409744 scopus 로고    scopus 로고
    • Vertical steam generator with an economizer section for VVÉR-1500
    • Podol'sk, November 19-23
    • V. V. Denisov, "Vertical steam generator with an economizer section for VVÉR-1500," in: Ensuring the Safety of Nuclear Power Plants with VVÉR Reactors, Podol'sk, November 19-23, 2001, Vol. 2, pp. 278-291.
    • (2001) Ensuring the Safety of Nuclear Power Plants with VVÉR Reactors , vol.2 , pp. 278-291
    • Denisov, V.V.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.