Annual Meeting on Safety and Licensing of Research Reactors 28 Aug - - PowerPoint PPT Presentation

annual meeting on safety and licensing of research
SMART_READER_LITE
LIVE PREVIEW

Annual Meeting on Safety and Licensing of Research Reactors 28 Aug - - PowerPoint PPT Presentation

Annual Meeting on Safety and Licensing of Research Reactors 28 Aug 1 Sept. 2016 Ahmed Zakareia Egypt Amal Hasan Elgahwaji Libya Amany Mohammed Ahamed Sudan Amr


slide-1
SLIDE 1

Annual Meeting on Safety and Licensing of Research Reactors 28 Aug – 1 Sept. 2016

Ahmed Zakareia Egypt Amal Hasan Elgahwaji Libya Amany Mohammed Ahamed Sudan Amr Khaled Shabka Egypt Khaled Abd Eltawab Egypt Walid Dridi Tunisia

1

slide-2
SLIDE 2

2

slide-3
SLIDE 3

PIE 10 MW reactor Subcritical Remarks (l) Loss of electrical power supplies: Loss of normal electrical power Applicable Applicable (2) Insertion of excess reactivity: Criticality during fuel handling (due to an error in fuel insertion) Applicable Not applicable Startup accident Applicable Not applicable Control rod failure or control rod follower failure Applicable Not applicable Control drive failure or system failure Applicable Not applicable

3

slide-4
SLIDE 4

PIE 10 MW reactor Subcritical Remarks Failure of other reactivity control devices (such as a moderator or reflector) Applicable Not applicable Unbalanced rod positions Applicable Not applicable Failure or collapse of structural components Applicable Not applicable Insertion of cold water Applicable Not applicable Changes in the moderator (e.g. voids or leakage of D2O into H2O systems) Applicable Not applicable

4

slide-5
SLIDE 5

PIE 10 MW reactor Subcritical Remarks Influence by experiments and experimental devices (e.g. flooding or voiding, temperature effects, insertion of fissile material or removal of absorber material Applicable Not applicable Insufficient shutdown reactivity Applicable Not applicable Inadvertent ejections of control rods Applicable Not applicable Maintenance errors with reactivity devices Applicable Not applicable Spurious control system signals Applicable Not applicable

5

slide-6
SLIDE 6

PIE 10 MW reactor Subcritical Remarks (3) Loss of flow: Primary pump failure Applicable Not applicable Reduction in flow of primary coolant (e.g. due to valve failure or a blockage in piping or a heat exchanger) Applicable Not applicable Influence of the failure or mishandling of an experiment Applicable Not applicable Rupture of the primary coolant boundary leading to a loss of flow Applicable Not applicable Fuel channel blockage Applicable Not applicable

6

slide-7
SLIDE 7

PIE 10 MW reactor Subcritical Remarks Improper power distribution due, for example, to unbalanced rod positions in core experiments or fuel loading (power–flow mismatch) Applicable Not applicable Reduction in coolant flow due to bypassing of the core Applicable Not applicable Deviation of system pressure from the specified limits Applicable Not applicable Loss of heat sink (e.g. due to the failure of a valve or pump or a system rupture). Applicable Not applicable

7

slide-8
SLIDE 8

PIE 10 MW reactor Subcritical Remarks (4) Loss of coolant: Rupture of the primary coolant boundary Applicable Not applicable Damaged pool Applicable Not applicable Pump-down of the pool Applicable Not applicable Failure of beam tubes or

  • ther penetrations

Applicable Not applicable

8

slide-9
SLIDE 9

PIE 10 MW reactor Subcritical Remarks (5) Erroneous handling or failure of equipment or components: Failure of the cladding of a fuel element Applicable Applicable Mechanical damage to core or fuel (e.g. mishandling of fuel and dropping of a transfer flask onto the fuel) Applicable Applicable Failure of a emergency cooling system Applicable Not applicable Malfunction of the reactor power control Applicable Not applicable Criticality in fuel in storage Applicable Not applicable

9

slide-10
SLIDE 10

PIE 10 MW reactor Subcritical Remarks Failure of means of confinement, including the ventilation system Applicable Applicable Loss of coolant to fuel during transfer or storage Applicable Not applicable Loss or reduction of proper shielding Applicable Applicable Failure of experimental apparatus or material (e.g. loop rupture) Applicable Not applicable Exceeding of fuel ratings Applicable Not applicable

10

slide-11
SLIDE 11

PIE 10 MW reactor Subcritical Remarks (6) Special internal events: Internal fires or explosions Applicable Applicable Internal flooding Applicable Applicable Loss of support systems Applicable Applicable Security related incidents Applicable Applicable Malfunctions in reactor experiments Applicable Applicable Improper access by persons to restricted areas Applicable Applicable Fluid jets and pipe whip Applicable Applicable Exothermic chemical reactions Applicable Applicable

11

slide-12
SLIDE 12

PIE 10 MW reactor Subcritical Remarks (7) External events: Earthquakes (including seismically induced faulting and landslides) Applicable Applicable Flooding (including failure of an upstream dam and blockage of a river) Applicable Applicable Tornadoes and tornado missiles; Applicable Applicable Sandstorms Applicable Applicable Hurricanes, storms and lightning Applicable Applicable Tropical cyclones Applicable Applicable

12

slide-13
SLIDE 13

PIE 10 MW reactor Subcritical Remarks Explosions Applicable Applicable Aircraft crashes Applicable Applicable Fires Applicable Applicable Toxic spills Applicable Applicable Accidents on transport routes Applicable Applicable Effects from adjacent facilities (e.g. nuclear facilities, chemical facilities and waste management facilities) Applicable Applicable Biological hazards such as microbial corrosion, structural damage or damage to equipment by rodents or insects Applicable Applicable

13

slide-14
SLIDE 14

PIE 10 MW reactor Subcritical Remarks Extreme meteorological phenomena Applicable Applicable Lightning strikes Applicable Applicable Power or voltage surges

  • n the external supply

line Applicable Applicable (8) Human errors Applicable Applicable

14