Revised Burnup Code System SWAT: Description and Validation Using Postirradiation Examination Data

Author:

Suyama Kenya1,Mochizuki Hiroki1,Kiyosumi Takehide2

Affiliation:

1. Japan Atomic Energy Research Institute, Department of Fuel Cycle Safety Research Tokai-mura, Naka-gun, 319-1195, Japan

2. Japan Research Institute, Ltd. Energy Technology Department, Ichiban-cho 16, Chiyoda-ku, Tokyo, 102-0082, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference30 articles.

1. OREST—The HAMMER-ORIGEN Burnup Program System: Method and Results

2. Y. NAITO, M. INAMURA, F. MASUKAWA, and Y. OKUDA, “UNITBURN: A Computer Code for Burnup Calculation of a Unit Fuel Cell,” JaErI-M 90 019, Japan Atomic Energy Research Institute (1990) (in Japanese).

3. R. L. MOORE, B. G. SCHNITZLER, C. A. WEMPLE, R. S. BABCOCK, and D. E. WESSOL, “MOCUP: MCNP-ORIGEN2 Coupled Utility Program,” INEL-95/0523, Idaho National Engineering Laboratory (1995).

4. Validation of a Continuous-Energy Monte Carlo Burn-up Code MVP-BURN and Its Application to Analysis of Post Irradiation Experiment

5. C. V. PARKS, “SCALE-4.3: Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation for Workstations and Personal Computers,” NUREG/CR-0200, Rev. 5 (ORNL/NUREG/CSD-2/R5) as CCC-545, Oak Ridge National Laboratory (1995).

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