Damage Calculation for First Wall Submitted to High Neutron Flux in a Tokamak

ABSTRACTThe displacement per atom (dpa) has been a specific issue to evaluate the damage in the first wall of the Tokamak. Two different first wall materials were evaluated. In this study, MCNP5 code was used to obtain the neutron flux, the energy deposition and the main reaction rates, on the inboard and outboard first wall. The damage calculations were performed by the SPECTER code using the neutronic parameters obtained by MCNP5. The Tokamak reactor modeled has similar dimensions to the ITER. Tungsten and beryllium alloys were simulated on the outboard first wall. The results indicate which material has a higher resistance to be damage and dpa values for the analyzed material.

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Investigation of the reactor’s high neutron flux effects on the physical and chemical characteristics of polymeric material

Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms ◽

10.1016/j.nimb.2019.10.011 ◽

2019 ◽

Vol 461 ◽

pp. 210-218

Author(s):

Elsayed K. Elmaghraby ◽

S.A. Abd El Aal ◽

O. Awny ◽

N.A. Mansour ◽

Nabil M. Hassan ◽

...

Keyword(s):

Neutron Flux ◽

Polymeric Material ◽

Chemical Characteristics ◽

Physical And Chemical Characteristics ◽

Physical And Chemical ◽

High Neutron ◽

High Neutron Flux

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Tests of electronic devices and semi-conductor detectors under high neutron flux

Journal of Physics Conference Series ◽

10.1088/1742-6596/41/1/002 ◽

2006 ◽

Vol 41 ◽

pp. 21-35

Author(s):

Ghislain Gregoire

Keyword(s):

Neutron Flux ◽

Electronic Devices ◽

High Neutron ◽

High Neutron Flux

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Anticipated Transient Without Scram Analysis for an ABWR Using RETRAN

Volume 3: Thermal Hydraulics; Instrumentation and Controls ◽

10.1115/icone16-48732 ◽

2008 ◽

Author(s):

Chiung Wen Tsai ◽

Shu Ming Yang ◽

Chunkuan Shih ◽

Jong-Rong Wang ◽

Shao Shih Ma ◽

...

Keyword(s):

High Pressure ◽

Control System ◽

Neutron Flux ◽

Transient Analysis ◽

Valve Closure ◽

The Third ◽

The Core ◽

Main Steam ◽

High Neutron ◽

High Neutron Flux

A RETRAN02/MOD5 model was developed for Lungmen ABWR and applied for ATWS transient analysis. Three ATWS events including Main Steam Isolation Valve Closure (MSIVC), Loss of Offsite Power (LOOP), and Inadvertent Opening of all Turbine Bypass Valves (IOTBV) are analyzed in this study. During the first two transients, the vessel pressure is increased as a result of steam flow reduction due to the closure of main steam isolation valves (MSIVs) and Turbine Control Valves (TCVs) respectively. In the third transient, the vessel pressure is reduced because of the open of Turbine Bypass Valves (TBVs) and turns to be increased because of the closure of MSIVs. All of the above transients suffer high neutron flux as a result of void reduction. There are several equipments and procedures to mitigate ATWS transient such as feedwater trip, Reactor Internal Pumps (RIPs) runback and trip, and the depressurization of relief valves. After the ATWS high pressure signal is initiated and permissive for 180 seconds, Standby Liquid Control system is initiated to inject boron liquid into upper plenum to shutdown the reactor. The results conclude that equipments and procedures mitigate the event effectively and the core is brought to shutdown state.

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