Evaluation of the Uncertainties in the Source Distribution for Pressure Vessel Neutron Fluence Calculations
Author:
Affiliation:
1. The Pennsylvania State University Nuclear Engineering Department, 231 Sackett Building University Park, Pennsylvania 16802
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT95-A35068
Reference16 articles.
1. Application of the LEPRICON Unfolding Procedure to the Arkansas Nuclear One-Unit 1 Reactor
2. M. EDENIUS et al. “CASMO-3, A Fuel Assembly Burnup Program,” Studsvik/NFA-86/7, Studsvik Energitehnik (Nov. 1986).
3. K. SMITH et al. “SIMULATE-3, Advanced Three-Dimensional Two-Group Reactor Analysis Code,” Studsvik/SOA-88/01, Studsvik of America (Mar. 1988).
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