A Core Design Study on the Fuel Displacement Options for an Effective Transition between Breakeven and TRU Burning Sodium-Cooled Fast Reactors-Reference-Cited by-同舟云学术

A Core Design Study on the Fuel Displacement Options for an Effective Transition between Breakeven and TRU Burning Sodium-Cooled Fast Reactors

Published:2014-06 Issue:3 Volume:186 Page:390-402
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Kim Sang Ji¹,Ha Pham Nhu Viet¹,Lim Jae Yong¹,Yang Won Sik²

Affiliation:

1. Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu Daejeon 305-353, Korea

2. Purdue University, School of Nuclear Engineering, West Lafayette, Indiana 47907-2017

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/NT13-90

Reference12 articles.

1. D. HAHN et al. “KALIMER-600 Conceptual Design Report,” KAERI/TR-3381/2007, Korea Atomic Energy Research Institute (2007).

2. J. D. KIM, “KAFAX-E66,” NDL-23/01, Nuclear Data Laboratory, Korea Atomic Energy Research Institute (2001).

3. R. E. MacFarlane, “TRANSX-2: A Code for Interfacing MATXS Cross Section Libraries to Nuclear Transport Codes,” LA-12312-MS, Los Alamos National Laboratory (1993).

4. R. E. ALCOUFFE, “User’s Guide for TWODANT: A Code Package for Two-Dimensional, Diffusion-Accelerated, Neutron Transport,” LA-10049-M, Los Alamos National Laboratory (1990).

5. B. J. TOPPEL, “A User’s Guide for the REBUS-3 Fuel Cycle Analysis Capability,” ANL-83-2, Argonne National Laboratory (1983).

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