Transcript

ZHANG Donghui, YU Hong, HUO Xingkai, HU Yun

China Institute of Atomic Energy (CIAE)

2015-5-28

1

Preliminary Proposal of a CRP Project of

Reactor Physics Benchmark of China

Experimental Fast Reactor (CEFR)

CONTENTS:

Scientific Scope of the Project2

3 Work Plan

Background1

2

4 Expected Outputs

1. Background� China Experimental Fast Reactor

3

−Sodium-cooled fast reactor with

nominal power of 65MWt

−Reached the first criticality at July

21, 2010

−Generated electricity at 40% full

power and was connected firstly

to the grid in July 2011

−Generated electricity at 100%

power and operated continuously

for 144 hours in Dec. 2015

1. Background� Reactor Core

4

MAIN PARAMETERS:

Name Value

Norminal power 65 MWt

Fuel UO2(64.4%)

Max.neutron flux E < 0.1MeV, 3.2×1015cm-2s-1

E > 0.1MeV, 2.5×1015cm-2s-1

Max./Ave. burnup 60.0/44.5 MWd/kg

Core height/diameter 450/600mm

Num. of Fuel SAs 81

UO2 mass 428kg

Max linear power 43 kW/m

Refuelling period 80 EFPDs

Staying time in the core of fresh fuel S.A.

inner,3Tr;outer,4 Tr.

1. Background

� Overview of CEFR physical startup experiments

5

−Starting from 5 June 2010, including 4 aspects of tests:

1. Fuel loading

and criticality

1. Fuel loading

and criticality

Net criticality

250℃(cold state)

360℃ (hot standby)

Nuclear heating start point

2. Measurement

of control rod

worth

2. Measurement

of control rod

worth

Net criticality core

Operation loading core (250℃)

Operation loading core (360℃)

3. Reactivity

effect

measurement

3. Reactivity

effect

measurement

Temperature reactivity coefficient

Pressure reactivity effect

Flowrate reactivity effect

Sodium void reactivity effect

Core SA exchange reactivity effect

4. Irradiation test

of foils

4. Irradiation test

of foils

Reaction rate distribution

Cross-section ratio

Neutron spectrum

Absolute nuclear power

1. Background

� Overview of CEFR physical startup experiments

6

− In CEFR physical startup experiments, a large amount of experiment

data was recorded and, in addition, respective calculations were

done for comparison.

−These data and results are one of the most important outcomes of

the CEFR project, and can benefit the nuclear world in code and data

validation and the development of analysis abilities on fast reactors.

To establish a reactor physics benchmark based on

CEFR physical startup experiment.

CONTENTS:

Scientific Scope of the Project2

3 Work Plan

Background1

7

4 Expected Outputs

2. Scientific Scope of the Project

� Overall objective

8

−To establish a benchmark based on CEFR start-up experiments, which

is helpful for the validation and verification of code and data used by

participating states;

−To contribute to the improvement of capabilities in the field of fast

reactor design and analysis.

2. Scientific Scope of the Project

� Specific objectives

9

− Firstly, collect and evaluate experiment data obtained from CEFR tset,

including :

• fueling and first criticality

• control rod worth measurements

• reactivity coefficients measurements

• irradiation foil tests

− Secondly, set up a simplified model of CEFR core, and make neutronics

calculations independently by participating institutes

− Thirdly, make a comparison of the experiment results and calculation results

of participating institutes, and make error analysis

− Fourthly, establish standard reactor physiscs benchmark documents

CONTENTS:

Scientific Scope of the Project2

3 Work Plan

Background1

10

4 Expected Outputs

3. Work plan� Five years plan (preliminary)

11

Work plan

2015

(Project

approval)

– Submit project proposal to IAEA

– Discuss and solidify the objective of the project

– Subscription of IAEA research contracts and proposals

2016

(CRP

Phase 1)

– CIAE will provide simplified CEFR neutronics core model of net

criticality state and description of the test to participants

– All participants will make criticality calculation

– Make comparison and analysis of results of calculation and test

– Draft and submit the annual report to IAEA

2017

(CRP

Phase 2)

– CIAE will provide simplified CEFR neutronics core model to

participants to make control rods worth calculation

– All participants will make control rod worth calculation

– CIAE will provide description and results of CEFR control rod

measurements, and then all participants make comparison and

analysis of results of calculation and test

– Draft and submit the annual report to IAEA

3. Work plan

12

Work plan

2018

(CRP

Phase 3)

– CIAE will provide simpified CEFR neutronics core model to participants

associated to the measurents of : 1) temperature reactivity effect ;2)

sodium void effect; 3) SAs exchange effect

– All participants will make calculation indepently

– CIAE will provide tests descriptions and results, and then all participants

make comparison and analysis of resutls of calculation and test

– Draft and submit the annual report to IAEA

2019

(CRP

Phase 4)

– CIAE will provide simplified CEFR neutronics core model to participants

associated to the irradiation foil tests

– All participants will make calculation independently

– CIAE will provide tests descriptions and results, and then all participants

make comparison and analysis of results of calculation and test

– Draft and submit the annual report to IAEA

� Five years plan (preliminary)

3. Work plan

13

Work plan

2020

(CRP

Phase 5)

– Dicusssion of the final output of the project by all participant

– Draft the final document of the CEFR benchmark

– International review of the CEFR benchmark and the final document

– Sodify the final document and submit to IAEA

� Five years plan (preliminary)

CONTENTS:

Scientific Scope of the Project2

3 Work Plan

Background1

14

4 Expected Outputs

4. Expected ouputs

� Expected outputs

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I. Sharing of CEFR reactor physical startup experiments and results to all

participants.

II. A standard and evaluated benchmark report, as an IAEA technical

publication or in any other appropriate publication form, based on CEFR

physical start-up experiments.

III. Validation and qualification of the codes and data used in fast reactor

design and analysis.

IV. Improvement of the abilities of participating states on fast reactor design

and analysis.

16

CEFR, the coming platform for R&D international cooperation.


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