References
- OECD/NEA (Ed.) . 2000 . The JEF-2.2 Nuclear Data Library , JEFF Report 17
- Shibata , K. 2002 . “Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3” . J. Nucl. Sci. Technol. , 39 : 1125
- Kinsey , R. 1979 . ENDF-102, Data Formats and Procedures for the Evaluated Nuclear Data File: ENDF, (ENDF/B-V), , 2nd ed. Brookhaven National Laboratory . BNL-NCS-50496
- Rose , P. F. 1991 . ENDF-201, ENDF/B-VI Summary Documentation, , 4th ed. Brookhaven National Laboratory . MOD1 New Evaluation (ENDF/B-VI), BNL-NCS-17541
- Okumura , K. and Mori , T. 2003 . Integral Test of JENDL-3.3 for Thermal Reactors , L2150A JAERI-CONF-2003–006 Japan Atomic Energy Research Institute (JAERI) .
- Kamei , T. and Yoshida , T. 1983 . “Error due to nuclear data uncertainties in the prediction of large liquid-metal fast breeder reactor core performance parameters” . Nucl. Sci. Eng. , 84 : 83
- Takeda , T. and Yoshimura , A. 1989 . “Prediction uncertainty evaluation methods of core performance parameters in large liquid-metal fast breeder reactors” . Nucl. Sci. Eng. , 103 : 157
- Elam , K. R. and Rearden , B. T. 2003 . “Use of sensitivity and uncertainty analysis to select benchmark experiments for the validation of computer codes and data” . Nucl. Sci. Eng. , 145 : 196
- Takeda , T. 2005 . “Analysis of uncertainty reduction of factor for determining critical mockup of an innovative long-life fast reactor” . In Proc. ICAPP'05 Seoul , , Korea May 15–19, p. E-5444
- Kugo , T. Kojima , K. 2005 . “Preliminary evaluation of reduction of prediction error in breeding light water reactor core performance” . In Proc. ICAPP'05 Seoul , , Korea May 15–19, p. E-5250
- Hara , A. Takeda , T. 1984 . SAGEP: Two-Dimensional Sensitivity Analysis Code Based on Generalized Perturbation Theory , JAERI-M 84–065 Japan Atomic Energy Research Institute (JAERI) . [in Japanese]