Benchmark analysis for EBR-II shutdown heat removal tests.

Format:

Book

Series:

IAEA-TECDOC ; Number 1819.

IAEA TECDOC Series, 1011-4289 ; Number 1819

Language:

English

Subjects (All):

Breeder reactors.

Physical Description:

1 online resource (465 pages) : illustrations (some color).

Edition:

1st ed.

Place of Publication:

Vienna, Austria : International Atomic Energy Agency, 2017.

Summary:

This publication presents the results and main achievements of an IAEA coordinated research project to verify and validate system and safety codes used in the analyses of liquid metal thermal hydraulics and neutronics phenomena in sodium cooled fast reactors. The publication will be of use to the researchers and professionals currently working on relevant fast reactors programmes. In addition, it is intended to support the training of the next generation of analysts and designers through international benchmark exercises

Contents:

Intro

1. Introduction

1.1. Objectives of the Coordinated Research Project

1.2. Procedure for Implementation of the CRP

2. Description of EBR-II

2.1. Reactor

2.2. Core

2.3. Heat transport systems

2.3.1. Primary heat transport system

2.3.2. Intermediate heat transport system

2.3.3. Water/steam system and turbines

2.4. Basic plant specifications

3. Description of the Shutdown Heat Removal Tests Conducted in 1984 and 1986

3.1. Test descriptions

3.1.1. SHRT-17

3.1.2. SHRT-45R

3.2. Description of instrumentation used for the tests

3.2.1. Temperature measurements

3.2.2. Flowmeters

3.2.3. Instrumented subassembly XX09

3.2.4. Instrumented subassembly XX10

3.2.5. Fission power measurement

3.2.6. Pressure measurements

3.3. Test results

3.3.1. SHRT-17

3.3.2. SHRT-45R

3.4. Interpretation of the experimental data used in the benchmark exercise

4. Benchmark Specifications

4.1. Plant parameters

4.2. Core data

4.2.1. Types of subassemblies

4.2.2. Fuel properties

4.3. Primary circuit

4.4. SHRT-45R neutronics benchmark specification

4.5. Output parameters to BE calculated

5. Description of Simulation Codes

5.1. Systems analysis codes

5.1.1. CATHARE (IRSN)

5.1.2. EBRDYN (IGCAR)

5.1.3. FRENETIC (Politecnico di Torino)

5.1.4. MARS-LMR (KAERI)

5.1.5. NETFLOW++ (U. of Fukui)

5.1.6. RELAP5-3D (ENEA, N.IN.E., U. of Fukui)

5.1.7. SAS4A/SASSYS-1 (Argonne, CIAE, TerraPower)

5.1.8. SAC-CFR (NCEPU)

5.1.9. SIMMER (KIT)

5.1.10. SOCRAT-BN (IBRAE)

5.1.11. SPECTRA (NRG)

5.1.12. Super-COPD (JAEA)

5.1.13. THACS (XJTU)

5.1.14. TRACE (KINS, NRG, PSI)

5.2. Neutronics codes

5.2.1. DIF3D (Argonne)

5.2.2. ERANOS (KIT, U. Fukui)

5.2.3. MC2-3 (Argonne)

5.2.4. MCNP6 (ENEA)

5.2.5. NJOY (U. Fukui)

5.2.6. PARTISN (KIT).

5.2.7. PHISICS (ENEA)

5.2.8. SCALE6.1 (ENEA)

5.2.9. SERPENT (Politecnico di Torino, PSI)

5.2.10. TRAIN (KIT)

5.2.11. VARI3D and PERSENT (Argonne)

5.3. Other types of codes

5.3.1. ANSYS CFX (ENEA, NRG, U. of Fukui)

5.3.2. ASFRE (JAEA)

5.3.3. COBRA4i (TerraPower, U. of Fukui)

5.3.4. STAR-CD (IGCAR)

5.3.5. Thermo-Calc (Kyushu university)

6. General Description of CRP Analysis Approach

6.1. Phase 1

6.2. Phase 2

7. Models and Results

7.1. China Institute of Atomic Energy (China)

7.1.1. Geometry/discretization

7.1.2. Nuclear and thermo-physical data/correlations

7.1.3. Thermal hydraulics methods and models

7.1.3.1. Code(s) used

7.1.3.2. Basic method

7.1.3.3. Model

7.1.4. Blind results

7.1.4.1. SHRT-17

7.1.4.2. SHRT-45R

7.1.5. Final results, data comparisons

7.1.5.1. SHRT-17

7.1.5.2. SHRT-45R

7.1.5.3. Model improvements

7.2. North China Electric Power University (China)

7.2.1. Geometry/discretization

7.2.2. Nuclear and thermo-physical data/correlations

7.2.3. Thermal hydraulics methods and models

7.2.3.1. Code(s) used

7.2.3.2. Basic method

7.2.3.3. Model

7.2.4. Blind results

7.2.5. Final results, data comparisons

7.2.5.1. SHRT-17

7.2.5.2. SHRT-45R

7.2.5.3. Model improvements

7.2.6. Neutronics methods and models

7.2.7. Neutronics results

7.3. Xi'an Jiaotong University (China)

7.3.1. Geometry/discretization

7.3.2. Nuclear and thermo-physical data/correlations

7.3.3. Thermal hydraulics methods and models

7.3.3.1. Code(s) used

7.3.3.2. Basic method

7.3.3.3. Model

7.3.4. Blind results

7.3.4.1. SHRT-17

7.3.4.2. SHRT-45R

7.3.5. Final results, data comparisons

7.3.5.1. SHRT-17

7.3.5.2. SHRT-45R

7.3.5.3. Model improvements

7.4. IRSN (France)

7.4.1. Geometry/discretization.

7.4.2. Thermal hydraulics methods and models

7.4.2.1. Code(s) used

7.4.2.2. Model

7.4.3. Blind results

7.4.3.1. SHRT-17

7.4.3.2. SHRT-45R

7.4.4. Final results, data comparisons

7.4.4.1. SHRT-17

7.4.4.2. SHRT-45R

7.4.4.3. Model improvements

7.4.5. Conclusions

7.5. KIT (Germany)/Kyushu University (Japan)

7.5.1. Geometry/discretization

7.5.2. Nuclear and thermo-physical data/correlations

7.5.3. Thermal hydraulics methods and models

7.5.3.1. Code(s) used

7.5.3.2. Basic method

7.5.4. Blind results

7.5.4.1. SHRT-17

7.5.4.2. SHRT-45R

7.5.5. Final results, data comparisons

7.5.5.1. SHRT-17

7.5.5.2. SHRT-45R

7.5.5.3. Model improvements

7.5.6. Neutronics methods and models

7.5.6.1. Code(s) used

7.5.6.2. Neutron and photon cross-sections

7.5.6.3. Calculation of power and keff

7.5.6.4. Calculation of reactivity feedback

7.5.7. Neutronics results

7.6. Indira Gandhi Centre for Atomic Research (India)

7.6.1. Geometry/discretization

7.6.2. Nuclear and thermo-physical data/correlations

7.6.3. Thermal hydraulics methods and models

7.6.3.1. Code(s) used

7.6.3.2. Basic method

7.6.3.3. Model

7.6.4. Blind results

7.6.4.1. SHRT-17

7.6.4.2. SHRT-45R

7.6.5. Final results, data comparisons

7.6.5.1. SHRT-17

7.6.5.2. SHRT-45R

7.6.5.3. Model improvements

7.7. ENEA (Italy)

7.7.1. Geometry/discretization

7.7.2. Nuclear and thermo-physical data/correlations

7.7.3. Thermal hydraulics methods and models

7.7.3.1. Code(s) used

7.7.3.2. Basic method

7.7.4. Blind results

7.7.4.1. SHRT-17

7.7.4.2. SHRT-45R

7.7.5. Final CRP results and comparisons with the experimental data

7.7.5.1. SHRT-17

7.7.5.2. Model improvements

7.7.6. Neutronics methods and models

7.7.6.1. Code(s) used

7.7.6.2. Neutron and photon cross-sections.

7.7.6.3. Calculation of power and keff

7.7.6.4. Calculation of reactivity feedback

7.7.7. Neutronics results

7.8. Nuclear and Industrial Engineering (Italy)

7.8.1. Geometry/discretization

7.8.2. Nuclear and thermo-physical data/correlations

7.8.3. Thermal hydraulics methods and models

7.8.3.1. Code(s) used

7.8.3.2. Basic method

7.8.3.3. Model

7.8.4. Blind results

7.8.4.1. SHRT-17

7.8.4.2. SHRT-45R

7.8.5. Final results, data comparisons

7.8.5.1. SHRT-17

7.8.5.2. Model improvements

7.8.6. Neutronics methods and models

7.9. Politecnico di Torino (Italy)

7.9.1. Geometry/discretization

7.9.2. Nuclear and thermo-physical data/correlations

7.9.3. Thermal hydraulics methods and models

7.9.3.1. Code(s) used

7.9.3.2. Basic method

7.9.3.3. Model

7.9.4. Blind results

7.9.4.1. SHRT-17

7.9.4.2. SHRT-45R

7.9.5. Final results, data comparisons

7.9.5.1. SHRT-17

7.9.5.2. SHRT-45R

7.9.5.3. Model improvements

7.9.6. Neutronics methods and models

7.9.6.1. Code(s) used

7.9.6.2. Neutron and photon cross-sections

7.9.6.3. Calculation of power and keff

7.9.6.4. Calculation of reactivity feedback

7.9.7. Neutronics results

7.10. Japan Atomic Energy Agency (Japan)

7.10.1. Geometry/discretization

7.10.2. Nuclear and thermo-physical data/correlations

7.10.3. Thermal-hydraulics methods and models

7.10.3.1. Code(s) used

7.10.3.2. Basic method

7.10.3.3. Model

7.10.4. Blind results

7.10.4.1. SHRT-17

7.10.4.2. SHRT-45R

7.10.5. Final results, data comparisons

7.10.5.1. SHRT-17

7.10.5.2. Model improvements

7.11. University of Fukui (Japan)

7.11.1. Geometry/discretization

7.11.2. Nuclear and thermo-physical data/correlations

7.11.3. Thermal hydraulics methods and models

7.11.3.1. Code(s) used

7.11.3.2. Basic method.

7.11.3.3. Model

7.11.4. Blind results

7.11.4.1. SHRT-17

7.11.4.2. SHRT-45R

7.11.5. Final results, data comparisons

7.11.5.1. SHRT-17

7.11.5.2. SHRT-45R

7.11.5.3. Model improvements

7.11.6. Neutronics methods and models

7.11.6.1. Code(s) used

7.11.6.2. Neutron and photon cross-sections

7.11.6.3. Calculation of power and keff

7.11.6.4. Calculation of reactivity feedback

7.11.7. Neutronics results

7.12. Korea Atomic Energy Research Institute (Republic of Korea)

7.12.1. Geometry/discretization

7.12.2. Nuclear and thermo-physical data/correlations

7.12.3. Thermal-hydraulics methods and models

7.12.3.1. Code(s) used

7.12.3.2. Basic method

7.12.3.3. Model

7.12.4. Blind results

7.12.4.1. SHRT-17

7.12.4.2. SHRT-45R

7.12.5. Final results, data comparisons

7.12.5.1. SHRT-17

7.12.5.2. SHRT-45R

7.12.5.3. Model improvements

7.12.6. Neutronics methods and models

7.13. Korea Institute of Nuclear Safety (Republic of Korea)

7.13.1. Geometry/discretization

7.13.2. Nuclear and thermo-physical data/correlations

7.13.3. Thermal hydraulics methods and models

7.13.3.1. Code(s) used

7.13.3.2. Basic method

7.13.3.3. Model

7.13.4. Blind results

7.13.4.1. SHRT-17

7.13.4.2. SHRT-45R

7.13.5. Final results, data comparisons

7.13.5.1. SHRT-17

7.13.5.2. Model improvements

7.14. NRG (Netherlands)

7.14.1. Geometry/discretization

7.14.2. Nuclear and thermo-physical data/correlations

7.14.3. Thermal hydraulics methods and models

7.14.3.1. Code(s) used

7.14.3.2. Basic method

7.14.3.3. Model

7.14.4. Blind results

7.14.4.1. SHRT-17

7.14.4.2. SHRT-45R

7.14.5. Final results, data comparisons

7.14.5.1. SHRT-17

7.14.5.2. SHRT-45R

7.14.5.3. Model improvements

7.14.6. Neutronics methods and models.

7.15. IBRAE-RAN (Russian Federation).

Notes:

Includes bibliographical references.

Description based on online resource; title from PDF title page (ebrary, viewed October 23, 2017).

ISBN:

92-0-138919-1

OCLC:

1005618609