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Estimation of the Buckling of 239Pu Fueled System from the Data of Composite 239Pu-235U Fueled Fast Critical Assembly

Journal Article · · Nippon Genshiryoku Gakkaishi
OSTI ID:4720544
 [1]
  1. Japan Atomic Energy Research Inst. (JAERI), Tokai (Japan)
Pu239- U235-fueled fast critical assemblies are of interest for the estimation of properties of Pu239-fueled assemblies because of safety considerations and/or limited plutonium availability. Numerical analysis for bare and reflected homogeneous cores and reflected Two-region cores are previously reported. It is concluded that the errors in the calculated critical size for a 5.0 vol % Pu239-fueled system reduce by more than a factor of about 10 to 20, if an accurate experimental value of critical size of a critical assembly fueled by 0.5 vol % Pu239 and 4.5 vol % U235 is known. A general mathematical formula, which is useful to explain the above conclusions more clearly, is obtained for bare homogeneous mixtures using multigroup diffusion approximation. In order to predict the critical radius for the bare homogeneous Pu system to an accuracy of 1%, the errors for the experimental value of critical radius must be less than 0.1% for VPu/VFuel = 0.05 and 0.2% for VPu/VFuel = where VPu and VFuel are the volume fractions of Pu239 and fuel (Pu239 + U235) respectively. For the reflected Two region cores, the experimental errors required for the above accuracy must be less than 0.5% for the ratio of central Pu239 core region volume to total core volume of 0.1.
Research Organization:
Japan Atomic Energy Research Inst. (JAERI), Tokai (Japan)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
NSA Number:
NSA-17-009180
OSTI ID:
4720544
Journal Information:
Nippon Genshiryoku Gakkaishi, Journal Name: Nippon Genshiryoku Gakkaishi Vol. 4; ISSN 0004-7120
Publisher:
Atomic Energy Society of Japan
Country of Publication:
Japan
Language:
English