Last edited by Gokazahn
Monday, May 4, 2020 | History

2 edition of Candu Fuel Behaviour Under Transient Conditions. found in the catalog.

Candu Fuel Behaviour Under Transient Conditions.

Atomic Energy of Canada Limited.

Candu Fuel Behaviour Under Transient Conditions.

by Atomic Energy of Canada Limited.

  • 119 Want to read
  • 13 Currently reading

Published by s.n in S.l .
Written in English


Edition Notes

1

SeriesAtomic Energy of Canada Limited. AECL -- 6092
ContributionsSegel, A.W.
ID Numbers
Open LibraryOL21970480M

The primary objective of CANDU in-core fuel management is to determine fuel-loading and fuel-replacement strategies to operate the reactor in a safe and reliable fashion while keeping the total unit energy cost low. Within this context, the specific objectives of CANDU in-core fuel File Size: 1MB. Computational Analysis of the Behaviour of Nuclear Fuel Under Steady State, Transient and Accident Conditions If you would like to learn more about the IAEA’s work, sign up for our weekly updates containing our most important news, multimedia and more.

3. DESCRIPTION OF EXPERIMENT The EXP-FIO experiment, performed in the NRX (National Research Experimental) reactor at the Chalk River Laboratories in , was a part of an experimental program on fuel performance under high-temperature transient conditions such as those associated with the onset of a loss-of-coolant accident (LOCA). The meeting, in Japan, focused on fuel behaviour and modelling under design basis accidents. Such a short interval of two years between these last two technical meetings emphasizes the importance of the subject and the urgency to accelerate the process of accident related fuel behaviour code development and verification.

IFPE/CANDU-FIO, CANDU experiment FIO Fuel Behaviour under LOCA Conditions: nea IFPE/CANDU-FIO, CANDU experiment FIO Fuel Behaviour under LOCA Conditions: nea IFPE/CANDU-IRDMR, In-Reactor Diameter Measuring RIG EXP-FIO and EXP-FIO Fuel Behaviour under LOCA Conditions: nea the disposal of spent CANDU fuel were addressed from the perspective of isotopic composition.2 It was noted that the economic incentive for reprocessing spent fuel from Light Water Reactors (LWR) is far greater than for reprocessing spent CANDU fuel because of the very low fissile content of CANDU spent fuel compared to that of LWR spent fuel.


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Candu Fuel Behaviour Under Transient Conditions by Atomic Energy of Canada Limited. Download PDF EPUB FB2

Λ Models the behaviour of CANDU fuel under normal operating conditions λ Main Input Requirements – Fuel element (pellet and sheath) dimensions & properties – Power/burnup history – Coolant conditions λ Important Output Parameters – Fission product distribution (gap, grain boundary and grain bound) – Internal gas pressure – Fuel temperatures.

Thermal behaviour of CANDU type fuel rods during steady state and transient operating conditions. Fuel failure behavior under rapid transient power conditions is important to reactor safety since it controls the severity of an accident and in some cases it Cited by: 5.

λ Transient Temperature – fuel temperature transients are a function of the initial (in-reactor) fuel temperatures, decay heating rate and heat removal rate – calculated by the REDOU computer code λ Fuel Element (Sheath) Failure – ejected fuel bundles are assumed to break into pieces – UO2 pellets Candu Fuel Behaviour Under Transient Conditions.

book assumed to be completely ejected from the sheathFile Size: KB. Fuel Behaviour under Transient and LOCA Conditions Proceedings of a Technical Committee Meeting Held in Halden, Norway, 10–14 September IAEA TECDOC (CD-ROM) No. For educational use only, no assumed liability. Fuel – December CHAPTER 17 Fuel Prepared by Mukesh Tayal and Milan Gacesa – Independent Consultants Learning Objectives The principal learning objectives of this chapter are: To gain a general understanding of the major mechanisms affecting fuel behaviour under normal operating conditions;File Size: 2MB.

Modelling of irradiated UO2 fuel behaviour under transient conditions Article in Journal of Nuclear Materials () June with Reads How we measure 'reads'. a The basic CANDU fuel de~ign. b The history of th~bundle design c The significant diffe,ences between CANDU* and LWR+ fuel d Bundle ~anufacture e Fissile and structural materials and coolants used DU fuel program f Fuel and l behaviour, and performance under irradiation g Fuel physics m.:magementFile Size: 2MB.

TABLE OF CONTENTS ♦ 1. Basic Characteristics of the CANDU Lattice ♣ The CANDU Lattice Cell ♣ The Moderator ♣ The Fuel ♣ The Coolant ♣ The Pressure-Tube Concept ♣ Fuel Burnup and Irradiation and Effect of Operating Conditions ♦ 2. The CANDU Reactivity Devices ♣ Liquid Zone Controllers ♣ Mechanical Control Absorbers ♣ Adjuster RodsFile Size: KB.

handling of new fuel • refuels the reactor remotely while it is operating at any level of power • transfers the irradiated fuel remotely from the reactor to the storage bay.

Fuel Changing The fuel changing operation is based on the combined use of two remotely controlled fuelling machines, one operating on each end of a fuel channel. Fuel Behavior in Limited and Severe Core Damage Accidents.

•Temperature increases due to reduced cooling, stored energy and decay power. •Fuel cladding balloons due to difference between internal gas pressure and coolant pressure. −Localized due to small free volume. •Fuel cladding failure by various mechanisms. Thermal behaviour under rapid transient conditions In a potential loss-of-coolant accident (LOCA) heat transfer coefficients (fuel-to-cladding and cladding-to-coolant) will change more rapidly.

In fact, one of the largest problems in a LOCA analysis is to predict the time variations of these two : G Horhoianu, D.V Ionescu, G Olteanu. Fuel Management in CANDU by B. Rouben Manager, Reactor Core Physics Branch AECL Presented at Chulalongkorn University Bangkok, Thailand, December Abstract Fuel management in CANDU reactors is discussed.

The variation of lattice reactivity with irradiation is shown. The various periods in the operating life of the reactor are Size: 1MB. Detailed understanding of fuel behaviour under steady state, transient and accident conditions is an important part of the analyses of the safety of the nuclear power plant.

Investigations of fuel behaviour are carried out in close connection with experimental research operation feedback and. Introduction The development of fuel models that predict fuel behaviour during postulated transient conditions in CANDU-PHW (Canada Deuterium Uranium-Pres- surized Heavy Water) reactors, and the supporting experimental program, have been influenced by the design of the reactor system and by the approach to safety by: 1.

SIMULATION OF CANDU FUEL THERMAL-HYDRAULIC BEHAVIOR DURING SPENT FUEL BAY LOSS OF COOLING EVENTS (Ref. //) code assesses the thermal-mechanical response of a CANDU fuel element under Transient Conditions It was simulated the behavior of a fuel element from the outer ring of typical fuel bundle discharged from core andFile Size: 2MB.

e Fissile and structural materials and coolants used in the CANDU fuel program f Fuel and material behaviour, and performance under irradiation g Fuel physics and management h Booster rods and reactivity mechanisms, Fuel procurement, organization and industry j Fuel costs k Summary * CANDU -Canadian Deuterium Uranium Reactor + LWR -Light Water ReactorFile Size: 8MB.

Overview of high-temperature fuel behaviour with relevance to CANDU fuel Article (PDF Available) in Journal of Nuclear Materials (1) October with Reads How we measure 'reads'. Under accident transient conditions, the fuel elements (as part of a bundle) will be subjected to a set of thermal and mechanical loads.

These loads can lead to fuel element bowing and/or elongation. The ELESTRES code is used in the fuel analysis to evaluate the fission product inventory and fuel behavior under normal operating condition and provide the initial transient coolant conditions. Gehl's model [ 12 ] is used to assess the amount of fission gas released from the fuel during the transient Cited by: 1.

This publication is the proceedings of a technical meeting on fuel behaviour and modelling under severe transient and loss of coolant accident (LOCA) conditions. It was attended by nuclear fuel specialists representing fuel vendors, nuclear utilities, research and development institutions and regulatory bodies.term storage and the associated handling of spent CANDU fuel are well proven, and economic with an extremely high degree of public and environmental protection.

In fact, both short-term (water-pool) and medium-term (dry canister) storage of CANDU fuel are comparable or File Size: KB.This paper presents an assessment of the integrity of CANDU spent fuel during dry storage in MACSTOR.

Based on review of the safety requirements for sheath integrity during dry storage, a fuel temperature limit for spent CANDU fuel stored in MACSTOR is specified. The spent fuel conditions prior to, and during dry storage are Size: 4MB.