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Volumn 144, Issue 2, 2003, Pages 115-128

Validation of minor actinide cross sections by studying samples irradiated for 492 days at the Dounreay Prototype Fast Reactor - I: Radiochemical analysis

Author keywords

[No Author keywords available]

Indexed keywords

ACTINIDES; ALPHA PARTICLES; DATA REDUCTION; GAMMA RAYS; IRRADIATION; MASS SPECTROMETRY;

EID: 0038240501     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE03-A2347     Document Type: Review
Times cited : (15)

References (13)
  • 7
    • 0037564941 scopus 로고    scopus 로고
    • Validation of minor actinide cross sections by studying samples irradiated for 492 days at the Dounreay Prototype Fast Reactor - II: Burnup calculations
    • K. TSUJIMOTO, N. KOHNO, N. SHINOHARA, T. SAKURAI, Y. NAKAHARA, T. MUKAIYAMA, and S. RAMAN, "Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor - II: Burnup Calculations," Nucl. Sci. Eng., 144, 2, 129 (2003).
    • (2003) Nucl. Sci. Eng. , vol.144 , Issue.2 , pp. 129
    • Tsujimoto, K.1    Kohno, N.2    Shinohara, N.3    Sakurai, T.4    Nakahara, Y.5    Mukaiyama, T.6    Raman, S.7
  • 8
    • 0024055469 scopus 로고
    • Anion-exchange separation of nd and the transplutonium elements in spent nuclear fuels for burn-up determination
    • S. USUDA and N. KOHNO, "Anion-Exchange Separation of Nd and the Transplutonium Elements in Spent Nuclear Fuels for Burn-Up Determination," Sep. Sci. Technol., 23, 1119 (1988).
    • (1988) Sep. Sci. Technol. , vol.23 , pp. 1119
    • Usuda, S.1    Kohno, N.2
  • 9
    • 0024496243 scopus 로고
    • Rapid preparation of high-resolution sources for alpha-ray spectrometry of actinides in spent fuel
    • N. SHINOHARA and N. KOHNO, "Rapid Preparation of High-Resolution Sources for Alpha-Ray Spectrometry of Actinides in Spent Fuel," Appl. Radiat. Isot., 40, 41 (1989).
    • (1989) Appl. Radiat. Isot. , vol.40 , pp. 41
    • Shinohara, N.1    Kohno, N.2
  • 11
    • 20244378053 scopus 로고
    • Standard test method for atom percent fission in uranium plutonium fuel (neodymium-148 method)
    • E321-79, Vol. 12.02, American Society for Testing and Materials
    • "Standard Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)," Annual Book of ASTM Standards, E321-79, Vol. 12.02, p.156, American Society for Testing and Materials (1985).
    • (1985) Annual Book of ASTM Standards , pp. 156
  • 12
    • 0001378131 scopus 로고
    • ORIGEN2: A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials
    • A. G. CROFF, "ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials," Nucl. Technol., 62, 335 (1983).
    • (1983) Nucl. Technol. , vol.62 , pp. 335
    • Croff, A.G.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.