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Title: Using the LEPRICON System to Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1

Abstract

The accurate estimation of fast (E {>=} 1 MeV) neutron vessel fluence is very important because it is a crucial factor for the reference nil-ductility temperature (NDT) shift ({Delta}RT{sub NDT}). Recently, there has been a growing interest in best-estimate vessel fluence in Korea as elsewhere due to the proposed life-extension programs of the nuclear power plants. In this paper we report the results of best-estimate evaluation of the vessel fluence at Ulchin nuclear unit 1 (Ulchin-1) in Korea. Ulchin-1 is a pressurized water reactor of the Framatome type rated at 2775 MW(thermal) and in operation since 1988. We used the LEPRICON code system. First, to validate LEPRICON, we have revisited a previous analysis of the VENUS-1 experiments using the ELXSIR library based on ENDF/B-V Mod 3, which has updated iron cross sections. Then, three surveillance tests performed at the plant were used in the LEPRICON analysis.

Authors:
; ;
Publication Date:
Research Org.:
Korea Advanced Institute of Science and Technology, Taejon (KR); Korea Power Engineering Company, Taejon (KR)
Sponsoring Org.:
none (US)
OSTI Identifier:
786226
Report Number(s):
ISSN 0003-018X; CODEN TANSAO
ISSN 0003-018X; CODEN TANSAO; TRN: US0109312
Resource Type:
Conference
Resource Relation:
Conference: 2000 Annual Meeting, San Diego, CA (US), 06/04/2000--06/08/2000; Other Information: Transactions of the American Nuclear Society, Volume 82; PBD: 4 Jun 2000
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; FAST NEUTRONS; NEUTRON FLUENCE; CROSS SECTIONS; NUCLEAR POWER PLANTS; ULCHIN-1 REACTOR; L CODES; AGE DEPENDENCE; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; VALIDATION; RADIATION MONITORING; EXPERIMENTAL DATA

Citation Formats

Nam Zin Cho, Hyeong Heon Kim, and Hae Ryong Hwang. Using the LEPRICON System to Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1. United States: N. p., 2000. Web.
Nam Zin Cho, Hyeong Heon Kim, & Hae Ryong Hwang. Using the LEPRICON System to Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1. United States.
Nam Zin Cho, Hyeong Heon Kim, and Hae Ryong Hwang. Sun . "Using the LEPRICON System to Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1". United States.
@article{osti_786226,
title = {Using the LEPRICON System to Evaluate Best-Estimate Vessel Fluence at Ulchin NPP Unit 1},
author = {Nam Zin Cho and Hyeong Heon Kim and Hae Ryong Hwang},
abstractNote = {The accurate estimation of fast (E {>=} 1 MeV) neutron vessel fluence is very important because it is a crucial factor for the reference nil-ductility temperature (NDT) shift ({Delta}RT{sub NDT}). Recently, there has been a growing interest in best-estimate vessel fluence in Korea as elsewhere due to the proposed life-extension programs of the nuclear power plants. In this paper we report the results of best-estimate evaluation of the vessel fluence at Ulchin nuclear unit 1 (Ulchin-1) in Korea. Ulchin-1 is a pressurized water reactor of the Framatome type rated at 2775 MW(thermal) and in operation since 1988. We used the LEPRICON code system. First, to validate LEPRICON, we have revisited a previous analysis of the VENUS-1 experiments using the ELXSIR library based on ENDF/B-V Mod 3, which has updated iron cross sections. Then, three surveillance tests performed at the plant were used in the LEPRICON analysis.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {6}
}

Conference:
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