-
1
-
-
33847402373
-
-
ASME, 2002. Standard for probabilistic risk assessment for nuclear power plant applications, draft report, the American society of mechanical engineers, ASME RA-S-2002.
-
-
-
-
2
-
-
33847389495
-
Thermal hydraulic behavior of a steam generator tube rupture accident with a total loss of the high pressure safety injection
-
Nara, Japan, PID N6P135, October
-
Han S.-J., and Yang J.-E. Thermal hydraulic behavior of a steam generator tube rupture accident with a total loss of the high pressure safety injection. Proceedings of the 6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6). Nara, Japan, PID N6P135, October (2004)
-
(2004)
Proceedings of the 6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6)
-
-
Han, S.-J.1
Yang, J.-E.2
-
4
-
-
33847383439
-
-
Han, S.H. et al., 1998. A private supporting report in level 1 PSA for Ulchin unit 3 & 4, KAERI.
-
-
-
-
5
-
-
0036602734
-
Thermal-hydraulic analyses of steam generator tube rupture accident for the KORI nuclear unit 1 pressurized thermal shock study
-
Hong S.-J., Kim J.-H., Kim Y.-S., and Park G.-C. Thermal-hydraulic analyses of steam generator tube rupture accident for the KORI nuclear unit 1 pressurized thermal shock study. Nucl. Technol. 138 (2002) 273-283
-
(2002)
Nucl. Technol.
, vol.138
, pp. 273-283
-
-
Hong, S.-J.1
Kim, J.-H.2
Kim, Y.-S.3
Park, G.-C.4
-
6
-
-
33847387750
-
-
INEL, 1995. RELAP5/MOD3.2 code manual, NUREG/CR-5535, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission.
-
-
-
-
7
-
-
0032599135
-
Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1
-
Jeong J.-J., et al. Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1. Ann. Nucl. Energy 26 18 (1999) 1161-1642
-
(1999)
Ann. Nucl. Energy
, vol.26
, Issue.18
, pp. 1161-1642
-
-
Jeong, J.-J.1
-
8
-
-
33847344854
-
-
KEPCO, 1996. Ulchin units 3&4 Final Safety Analysis Report, Korea Electric Power Company.
-
-
-
-
9
-
-
33847357929
-
-
KEPCO, 1998. Ulchin units 3&4 probabilistic safety assessment, Korea Electric Power Company.
-
-
-
-
10
-
-
33847392205
-
-
KHNP, 1997. Ulchin units 3 & 4 emergency operate procedure, Korea Hydraulic and Nuclear Power Co.
-
-
-
-
11
-
-
0032615532
-
RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following SBLOCAs with totally failed HPI
-
Kumamaru H., Kukita Y., and Asaka H. RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following SBLOCAs with totally failed HPI. Nucl. Technol. 126 (1999) 331-339
-
(1999)
Nucl. Technol.
, vol.126
, pp. 331-339
-
-
Kumamaru, H.1
Kukita, Y.2
Asaka, H.3
-
12
-
-
0026908593
-
COBRA/RELAP5; A merged version of the COBRA-TF and RELAP5/MOD3 codes
-
Lee S.Y., et al. COBRA/RELAP5; A merged version of the COBRA-TF and RELAP5/MOD3 codes. Nucl. Technol. 99 (1992) 177-187
-
(1992)
Nucl. Technol.
, vol.99
, pp. 177-187
-
-
Lee, S.Y.1
-
15
-
-
33847420028
-
The effect of an aggressive cool-down following a refueling outage accident in which a pressurizer safety valve is stuck open
-
Lim H., Park J., and Jang S. The effect of an aggressive cool-down following a refueling outage accident in which a pressurizer safety valve is stuck open. J. Kor. Nucl. Soc. vol. 36 No. 6 (2004) 497-511
-
(2004)
J. Kor. Nucl. Soc.
, vol.36
, Issue.6
, pp. 497-511
-
-
Lim, H.1
Park, J.2
Jang, S.3
-
16
-
-
0034140505
-
Experimental investigation of early initiation of primary cooldown by secondary-side depressurization in a PWR inadequate core-cooling accident
-
Liu T.-J., Chan Y.-K., Ferng Y.-M., and Chang C.-Y. Experimental investigation of early initiation of primary cooldown by secondary-side depressurization in a PWR inadequate core-cooling accident. Nucl. Technol. 129-2 (2000) 187
-
(2000)
Nucl. Technol.
, vol.129-2
, pp. 187
-
-
Liu, T.-J.1
Chan, Y.-K.2
Ferng, Y.-M.3
Chang, C.-Y.4
-
17
-
-
33847407216
-
-
Park, J., 2003. A private communication about the human reliability in an ADV operation.
-
-
-
-
18
-
-
33847385596
-
-
Park, J.-H., 2003. A private communication with the senior operators in Yonggwang Unit 3.
-
-
-
-
19
-
-
19044383722
-
Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR
-
Son Y., et al. Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR. Nucl. Eng. Des. 235 (2005) 1571-1581
-
(2005)
Nucl. Eng. Des.
, vol.235
, pp. 1571-1581
-
-
Son, Y.1
-
20
-
-
33847358881
-
-
USNRC, 1987. Format and content of plant-specific pressurized thermal shock safety analysis reports for pressurized water reactor, U.S. Nuclear Regulatory Commission, Regulatory Guide 1.154.
-
-
-
-
21
-
-
33847409907
-
-
USNRC, 1998a. An approach for using probabilistic risk assessment in risk-informed decisions on plant-specific changes to the licensing basis, U.S. Nuclear Regulatory Commission, Regulatory Guide 1.174.
-
-
-
-
22
-
-
33847347028
-
-
USNRC, 1998b. An approach for plant-specific, risk-Informed decisionmaking: Technical specifications, U.S. Nuclear Regulatory Commission, Regulatory Guide 1.177.
-
-
-
|