NUCLEAR SAFETY REACTOR
Thread Rating:
  • 0 Vote(s) - 0 Average
  • 1
  • 2
  • 3
  • 4
  • 5
seminar surveyer
Active In SP
**

Posts: 3,541
Joined: Sep 2010
#1
24-12-2010, 11:08 AM


SUBMITTED BY: HITENDRA KATIYAR


.pptm   NUCLEAR SAFETY REACTOR.pptm (Size: 1.96 MB / Downloads: 70)



INTROCUCTION & MOTIVATION
This project and implimentation is based on Nuclear research for making Nuclear Reactor more secure.
Computational Fluid Dynamics (CFD) is increasingly being used in nuclear reactor safety (NRS) analyses as a tool that enables safety relevant phenomena occurring in the reactor coolant system.
Our Dept. Kannan Iyer having some research work on this NRS analysis.

PROJECT AIMS:
To prevent prompt effects of Nuclear reactor’s radiation with a high degree of assurance and minimize the risk of delayed effects.
Seismic Criteria for Siting Nuclear Power Plants.
Safety of Reactor Coolant Piping.
Assessments for Transporting Spent Nuclear Fuel.
Identifying Risks of Using Nuclear Medical Devices
Implementation challenges in adopting new technology.
Reactor Fuel Behavior and High Burn up Fuel
Plant Aging
Plant Material Conditions


WHY NUCLEAR SAFETY??
Nuclear safety covers the actions taken to prevent nuclear and radiation accidents or to limit their consequences.
This covers nuclear power plants, the transportation of nuclear materials, and the use and storage of nuclear materials for medical, power, industry, and military uses.
Nuclear and radiation accidents
New nuclear reactor designs are expected to have a higher level of safety than current designs
Improving safety management and promoting safety culture in operating organizations

COMPUTATIONAL NUCLEAR REACTOR ENGINEERING
PROBLEMS WITH OLD DESIGNS:

uncontrolled power excursion.
Loss of coolant resulting nuclear meltdown.
heat generated immense pressure can build up in the reactor vessel, resulting in a steam explosion resulting Cherbonyl.
Defueling – Fueling time avoids boiling crisis

PRELIMINARY SYSTEM ANALYSIS
POSSIBLE IMPROVEMENTS-

Confidence in reactor safety margins
Predictability of rare events
Fundamental well posed hyperbolic, conservative model ensuring objectivity.
Adaptive model refinement
Parallelized computation, non linear, implicit solvers
DNA – free of disease
Hard wired models and “lego” body.
Gap tooth simulation platform for reactor analysis
Stopping the movement of Radioactivity by using physical barriers and preventing fuel overheating


RESEARCHES IN DEPT.
Reactor Fuel Behavior and High Burn up Fuel : demonstrate that fuel damage would be limited and to confirm increases in energy output or the use of new cladding alloys in the fuel rods preserve the limits on fuel damage.

Plant Aging :The research is currently focused on the age-related degradation of passive components such as cables, connectors, and penetrations.

3. Plant Material Conditions : This research is focused on measuring, evaluating, and predicting the effects on structural integrity of nuclear systems, structures, and components (e.g., reactor pressure vessel and internals, and steam generator tubes)

4.Digital Instrumentation and Controls : The research is focused on evaluating these changes to digital controls, their possible safety implications.

5. Thermal Hydraulic and Severe Accident Computer Codes : Thermal-hydraulic research activities at NRC focus on the development of computer codes that simulate the behavior of the reactor system to ensure that a balance between energy removal from the fuel to the coolant is balanced by energy production in the fuel.

6. Probabilistic Risk Analysis : PRA research program contributes to the implementation of this policy in that it applies current methods and data to the resolution of reactor safety issues and develops and demonstrates new state-of-the-art PRA methods.

7. Radiation Protection :The radiation protection research program collects, analyzes, and disseminates information on occupational exposures reported to NRC by licensees.

8. Human Performance : The Human Performance Research program focuses on the interaction of people with the systems and the environments in which they work.

9. State-of-the-Art Reactor Consequence Analyses: The State-of-the-Art Reactor Consequence Analyses (SOARCA) program involves the reanalysis of severe accident consequences to develop a body of knowledge regarding the realistic outcomes of severe reactor accidents. the objective of this updated plant analysis is to include the significant plant safety improvements and updates, which have been made by plant owners but were not reflected in earlier assessments.


Reply

Important Note..!

If you are not satisfied with above reply ,..Please

ASK HERE

So that we will collect data for you and will made reply to the request....OR try below "QUICK REPLY" box to add a reply to this page

Quick Reply
Message
Type your reply to this message here.


Image Verification
Please enter the text contained within the image into the text box below it. This process is used to prevent automated spam bots.
Image Verification
(case insensitive)

Possibly Related Threads...
Thread Author Replies Views Last Post
  F1 Track Design and Safety Report seminar flower 0 434 30-10-2012, 02:03 PM
Last Post: seminar flower
  Laser Safety in Sight seminar flower 0 336 22-10-2012, 04:32 PM
Last Post: seminar flower
  CURRENT TRENDS in POWER GENERATION USING NUCLEAR FUEL seminar tips 0 385 09-10-2012, 05:06 PM
Last Post: seminar tips
  Fabrication of auto-braking system for pre-crash safety using sensor smart paper boy 1 2,312 14-02-2012, 01:14 PM
Last Post: seminar paper
  Nuclear Reactor Thermal-Hydraulics & Safety seminar class 0 1,676 08-03-2011, 02:30 PM
Last Post: seminar class
  SAFETY AIRBAGS IN CARS seminar surveyer 0 2,169 13-10-2010, 10:28 AM
Last Post: seminar surveyer
  VEHICLE GAS DETECTION WITH AUTOMATIC SAFETY WARNING SYSTEM full report seminar topics 1 3,314 18-08-2010, 07:57 PM
Last Post: r_guna_sekar