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Safety design process and implementation of

SDC for demonstration SFR

Fourth Joint IAEA-GIF Technical Meeting/Workshop on SAFETY OF SODIUM-COOLED FAST REACTORS

10 – 11 June 2014, Vienna

Outline

• Utility requirements

• Safety design process

• Implementation of SDC

2

Utility requirements

Safety Performance

3

•DiDSafety

•Plant Characteristics

•Transient response

•Reliability and availability

•Operability and maintainability

•constructibility

Performance

4

Utility requirements

G-III ALWR safety requirements

5

DiD

• Accident resistance

• Core damage

prevention

• Mitigation

LDB

• Regulatory imposed

margin

• In-service

inspection and

testing

• Safety system to

meet regulatory

requirements

• Containment and

associated systems

SMB

• Increased margin

• Simplicity

• System and

component

reliability

• Safety system

features for

investment

protection

• Containment

performance during

severe accident

Comparison between SFR and G-III

6

G-III ALWR SFR

Accident resistance

�License design basis

�Safety margin basis

Core damage prevention

�License design basis

�Safety margin basis

Mitigation

�License design basis

�Safety margin basis

For LWR, the reactor core shall be capable of

withstanding SBO for at least 8 hours without fuel

damage.

Outline

• Utility requirements

• Safety design process

• Implementation of SDC

7

Safety design

• Safe design means the integration of control

measures in the design process to eliminate or, if

this is not reasonable practicable, minimize risks

to human and investment throughout the life of the

power plant being designed.

• Characteristics of Safety:

Industry field

A kind of process state

Relative safe

Coexist with risk

Dynamical standard

8

System safety

• The application of engineering and

management principles, criteria, and

techniques to optimize safety within the

constraints of operational effectiveness,

time, and cost throughout all phases of the

system life cycle.

9

Safety design approach

• Designers determine which hazards could

be present, the level of associated risk that

could constitute danger, and the controls

or measures to assure acceptable risk.

• A step - by - step procedure for solving

problems; a decision making process

which moves from the general to the

specific; an iterative process.

10

Safety design process

• The main task is to predict,evaluate and

control risk.

11

Risk

identifica

tion and

prediction

Safety

analysis

Schemes

and

measures

comparison

Evaluation

Decision

making

Safety design process

• Category of NPP safety

• Nuclear safety

• SSC safety

• Building safety

• I&C safety

• Utility safety

• Plant site safety

12

Safety design process

• Safety analysis method

• Failure Modes and Effects Analysis(FMEA)

• Hazard and Operability Studies(HAZOP)

• Fault Tree Analysis(FTA)

• Event Tree Analysis(ETA)

13

Safety design process• Failure Modes and Effects Analysis(FMEA)

14

Assessment format

Safety design process

15

Divide system

Risk

identification

and prediction

Safety analysis

Schemes and

measures

comparison

EvaluationMeasurement

Effect

analysis

Decision

making

An iterative process

Safety design process

16

Outline

• Utility requirements

• Safety design process

• Implementation of SDC

17

Implementation of SDC

• 1 meeting between CIAE and NNSA.

• One debate for sodium void coefficient

• GIF-SFR-SDC will be an important reference for

regulatory body and designers.

• For designers, SDC is a kind of requirements and

boundary.

18

•DiD

•GIF-SFR-SDC

•G-III or G-IV

Safety

•Plant Characteristics

•Transient response

•Reliability and availability

•Operability and maintainability

•Constructibility

Performance

19

Implementation of SDC

Top-tier design requirement is almost finished.

Pre-conceptual design of demonstration SFR

Containment

Coolant System

Reactor Core

20

Implementation of SDC

21

Reactor Core Coolant system Containment

Safety √ √ √

Plant

Characteristics

Transient

response

Reliability and

availability

Operability and

maintainability

Constructibility

Implementation of SDC

22

Reactor Core Coolant system Containment

Safety Criterion 43,

44, 45, 46

Criterion 47,

48, 49, 50, 51,

53

Criterion 54,

55, 56, 57, 58

Plant

Characteristics

√ √ √

Transient

response

√ √ √

Reliability and

availability

√ √ √

Operability and

maintainability

√ √ √

Constructibility √ √ √

Implementation of SDC

System design requirement is under development.

Thank you for your attention!

23

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