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Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger; Central nuclar Atucha I. Intervencion al intercambiador nro2 del moderador

Abstract

Atucha I nuclear power plant moderator system operates with highly radioactive heavy water, a pressure of 115 Bar and temperatures of about 200 C degrees. In March 2000, an increasing leakage of heavy water to the conventional thermal circuit was detected, conducting the plant to a shut down. The development of a number of actions and measures were taken, in order to plug this leakage. The leakage was found in a heat exchanger, which is located in a place of difficult access, with a high radiological yield and which, according to design, it was not considered to be mechanically repaired. It is a U bend tubes heat exchanger, weighting about 20 tons, and with a heavy water flow of 800 tons/h on the primary circuit, and 950 tons/h of ordinary water on the secondary side. Foreseeing this event, it had been designed and constructed special equipment and procedures, by means of a contract, with the Company INVAP SA. Repair works were carried out within a period of eighty-six (86) days, from which, forty five days were used to repair the component itself. A considerable amount of time was used to prepare simulators and the training of personnel. Due to the  More>>
Authors:
Olivieri, Luis E; Zanni, Pablo A [1] 
  1. Nucleoelectrica Argentina SA (NASA), Lima (Argentina). Central Nuclear Atucha 1
Publication Date:
Jul 01, 2000
Product Type:
Conference
Report Number:
INIS-AR-C-282
Resource Relation:
Conference: AATN 2000: 27. Annual meeting of the Argentine Association of Nuclear Technology (AANT), AATN 2000: 27. Reunion anual de la Asociacion Argentina de Tecnologia Nuclear (AATN), Buenos Aires (Argentina), 22-24 Nov 2000; Other Information: figs., tabs; PBD: 2000
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ATUCHA REACTOR; HEAT EXCHANGERS; MAINTENANCE; REACTOR COOLING SYSTEMS; REPAIR
OSTI ID:
20308489
Country of Origin:
Argentina
Language:
Spanish
Other Identifying Numbers:
TRN: AR02C0172070653
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
28 pages
Announcement Date:
Dec 23, 2002

Citation Formats

Olivieri, Luis E, and Zanni, Pablo A. Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger; Central nuclar Atucha I. Intervencion al intercambiador nro2 del moderador. Argentina: N. p., 2000. Web.
Olivieri, Luis E, & Zanni, Pablo A. Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger; Central nuclar Atucha I. Intervencion al intercambiador nro2 del moderador. Argentina.
Olivieri, Luis E, and Zanni, Pablo A. 2000. "Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger; Central nuclar Atucha I. Intervencion al intercambiador nro2 del moderador." Argentina.
@misc{etde_20308489,
title = {Atucha I nuclear power plant: repair works in QK02W01 moderator system heat exchanger; Central nuclar Atucha I. Intervencion al intercambiador nro2 del moderador}
author = {Olivieri, Luis E, and Zanni, Pablo A}
abstractNote = {Atucha I nuclear power plant moderator system operates with highly radioactive heavy water, a pressure of 115 Bar and temperatures of about 200 C degrees. In March 2000, an increasing leakage of heavy water to the conventional thermal circuit was detected, conducting the plant to a shut down. The development of a number of actions and measures were taken, in order to plug this leakage. The leakage was found in a heat exchanger, which is located in a place of difficult access, with a high radiological yield and which, according to design, it was not considered to be mechanically repaired. It is a U bend tubes heat exchanger, weighting about 20 tons, and with a heavy water flow of 800 tons/h on the primary circuit, and 950 tons/h of ordinary water on the secondary side. Foreseeing this event, it had been designed and constructed special equipment and procedures, by means of a contract, with the Company INVAP SA. Repair works were carried out within a period of eighty-six (86) days, from which, forty five days were used to repair the component itself. A considerable amount of time was used to prepare simulators and the training of personnel. Due to the high radiological yield and the strict care of radiological standards, it was necessary the participation of 300 persons, integrating a collective dose of 4,86 Sv-m. It was necessary the construction of platforms and auxiliary stairs so as to make the work place accessible, as well as lifting and movement devices for heavy components, since this area does not have such kind of facilities. Welding and cutting machines remote controlled as well as manipulators which operated in front of the exchanger tube sheet were used. The aim was the reduction of dose values as much as possible. Special shielding were developed and in some cases it was necessary the adoption of drastic measures such as the cutting of bolts or pipes. The failure was detected and the tube was plugged. Also were plugged those tubes with wall thickness reduction (46 tubes). The exchanger has 1049 tubes. Personnel involved in the repair works came from different areas: Atucha I/II nuclear power plants, SPC Department, Embalse nuclear power plant, NASA Headquarters, CNEA and INVAP specialists. (author)}
place = {Argentina}
year = {2000}
month = {Jul}
}