Published September 2014 | Version v1
Report

Fuel Cooling in Absence of Forced Flow at Shutdown Condition with PHTS Partially Drained

  • 1. Cernavoda Nuclear Power Plant, Cernavoda (Romania)

Description

During the plant outage for maintenance on primary side (e.g. for the main Heat Transport System pumps maintenance, the Steam Generators inspection), there are situations which require the primary heat transport system (HTS) drainage to a certain level for opening the circuit. The primary fuel heat sink for this configuration is provided by the shutdown cooling system (SDCS). In case of losing the forced cooling (e.g. due to the loss of SDCS, design basis earthquake-DBE), flow conditions in the reactor core may become stagnant. Inside the fuel channels, natural circulation phenomena known as Intermittent Buoyancy Induced Flow (IBIF) will initiate, providing an alternate heat sink mechanism for the fuel. However, this heat sink is effective only for a limited period of time (recall time). The recall time is defined as the elapsed time until the water temperature in the HTS headers exceeds a certain limit. Until then, compensatory measures need to be taken (e.g. by re-establishing the forced flow or initiate Emergency Core Cooling system injection) to preclude fuel failures. The present paper briefly presents the results of an analysis performed to demonstrate that fuel temperature remains within acceptable limits during IBIF transient. One of the objectives of this analysis was to determine the earliest moment since the reactor shut down when maintenance activities on the HTS can be started such that IBIF is effective in case of losing the forced circulation. The resulting peak fuel sheath and pressure tube temperatures due to fuel heat up shall be within the acceptable limits to preclude fuel defect or fuel channel defects.Thermalhydraulic circuit conditions were obtained using a CATHENA model for the primary side of HTS (drained to a certain level), an ECC system model and a system model for SDCS. A single channel model was developed in GOTHIC code for the fuel assessment analysis. (author)

Part of:
Pressurized Heavy Water Reactor Fuel: Integrity, Performance and Advanced Concepts. Proceedings of the Technical Meetings held in Bucharest, 24-27 September 2012, and in Mumbai, 8-11 May 2013

Additional details

Publishing Information

ISBN
978-92-0-158414-4
Imprint Title
Pressurized Heavy Water Reactor Fuel: Integrity, Performance and Advanced Concepts. Proceedings of the Technical Meetings held in Bucharest, 24-27 September 2012, and in Mumbai, 8-11 May 2013
Imprint Pagination
[1 CD-ROM]
Journal Page Range
p. 73-85
ISSN
1684-2073
Report number
IAEA-TECDOC-CD--1751

Conference

Title
Integrity, Performance and Advanced Concepts
Acronym
Technical Meetings on Pressurized Heavy Water Reactor Fuel
Dates
24-27 Sep 2012; 8-11 Apr 2013
Place
Bucharest (Romania); Mumbai (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
46015493
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COOLING; COOLING SYSTEMS; ECCS; FOSSIL FUELS; HEAT SINKS; NUCLEAR FUELS; REACTOR CORES; REACTOR MAINTENANCE; SHUTDOWN; STEAM GENERATORS
Descriptors DEC
BOILERS; ENERGY SOURCES; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; FUELS; MAINTENANCE; MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTOR PROTECTION SYSTEMS; SINKS; VAPOR GENERATORS

Optional Information

Notes
15 figs.