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Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA

Technical Report:

Abstract

In PWR a 17x17 type fuel assembly is also used in place of the 15x15 type one. In order to evaluate the applicability of the results from 15x15 type simulated fuel assemblies to an actual reactor analysis, it is necessary to make clear the effect of the fuel assembly configuration and the fuel rod configuration. In this study, experiments using small scale reflood test facility were carried out by changing the rod bundle configuration, the grid spacer type and the fuel rod configuration systematically. The effect of each parameter on the core thermal-hydraulics was examined by comparing the experimental data and by using analytical results with REFLA/TRAC code which is applicable to the 15x15 type fuel assembly. The following conclusions were derived from this study: (1) As for the rod bundle configuration, the heat transfer and the void fraction models in REFLA/TRAC can predict the thermal-hydraulics in the 17x17 type fuel assembly within the same error band as for the 15x15 type one. (2) As for the grid spacer type, no significant effects are recognized for the peak clad temperature. The heat transfer and the void fraction models in REFLA/TRAC are applicable regardless of the grid spacer type. Although quench  More>>
Authors:
Ohnuki, Akira; Akimoto, Hajime; Iguchi, Tadashi; Murao, Yoshio [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Aug 01, 1994
Product Type:
Technical Report
Report Number:
JAERI-Research-94-012
Reference Number:
SCA: 210200; PA: JPN-94:011253; EDB-95:007384; SN: 95001296287
Resource Relation:
Other Information: PBD: Aug 1994
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; THERMODYNAMICS; CORE FLOODING SYSTEMS; HYDRODYNAMICS; PWR TYPE REACTORS; LOSS OF COOLANT; REACTOR CORES; FUEL ASSEMBLIES; FUEL RODS; CONFIGURATION; SIMULATION; 210200; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10102947
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE95722095; TRN: JP9411253
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
68 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, and Murao, Yoshio. Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA. Japan: N. p., 1994. Web.
Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, & Murao, Yoshio. Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA. Japan.
Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, and Murao, Yoshio. 1994. "Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA." Japan.
@misc{etde_10102947,
title = {Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA}
author = {Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, and Murao, Yoshio}
abstractNote = {In PWR a 17x17 type fuel assembly is also used in place of the 15x15 type one. In order to evaluate the applicability of the results from 15x15 type simulated fuel assemblies to an actual reactor analysis, it is necessary to make clear the effect of the fuel assembly configuration and the fuel rod configuration. In this study, experiments using small scale reflood test facility were carried out by changing the rod bundle configuration, the grid spacer type and the fuel rod configuration systematically. The effect of each parameter on the core thermal-hydraulics was examined by comparing the experimental data and by using analytical results with REFLA/TRAC code which is applicable to the 15x15 type fuel assembly. The following conclusions were derived from this study: (1) As for the rod bundle configuration, the heat transfer and the void fraction models in REFLA/TRAC can predict the thermal-hydraulics in the 17x17 type fuel assembly within the same error band as for the 15x15 type one. (2) As for the grid spacer type, no significant effects are recognized for the peak clad temperature. The heat transfer and the void fraction models in REFLA/TRAC are applicable regardless of the grid spacer type. Although quench velocity model slightly overestimates the quench velocity in the case of grid spacer type of 17x17 type fuel assembly under a low flooding velocity, the difference of the quench velocity between the grid spacer types does not affect the peak clad temperature and the core thermal-hydraulics can be predicted by REFLA/TRAC with good accuracy regardless of the grid spacer type. (3) As for the fuel rod configuration, the effect of the gap is small and the cladding material has a dominant effect. The REFLA/TRAC code is almost able to predict the effect of difference of the fuel rod configuration. From these conclusions, we consider that the results from the 15x15 type simulated fuel assemblies can apply to the evaluation of safety analyses for actual PWRs.}
place = {Japan}
year = {1994}
month = {Aug}
}