The accelerator-driven subcritical reactor system (ADS) is a kind of nuclear reactor which can burn minor actinide waste products produced from conventional reactors with inherent safety features. In this paper, the thermal-hydraulic model and a corresponding program for a 10 MW helium-cooled experimental ADS are presented. Through the analysis of the heat transfer mechanism in ADS, the thermal-hydraulic model of ADS was built, in which the solid domain is simulated with three-dimensional heat conduction model and the fluid domain is simulated with the one-dimensional quasi-static model. In order to analyze the transient characteristics of ADS with cooling system, a RELAP5–TRCAP coupling model for the cooling system was established, in which the decay heat of the target and core is considered. The results of steady condition and transients demonstrate the effectiveness of the transient model.

References

1.
Rubbia
,
C.
,
Rubio
,
J. A.
,
Buono
,
S.
,
Carminati
,
F.
,
Fietier
,
N.
,
Galvez
,
J.
,
Geles
,
C.
,
Kadi
,
Y.
,
Klapisch
,
R.
,
Mandrillon
,
P.
,
Revol
,
J. P.
, and
Roche
,
C. H.
,
1995
, “
Conceptual Design of a Fast Neutron Operated High Power Energy Amplifier
,” Report No. CERN/AT/95-44(ET).
2.
NEA-OECD
,
2002
, “
Accelerator-Driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles
,”
Report No. nea-3109
.
3.
The European Technical Working Group on ADS
,
2001
, “
A European Roadmap for Developing Accelerator Driven Systems (ADS) for Nuclear Waste Incineration
,”
ENEA
,
Rome, Italy
.
4.
Cinotti
,
L.
,
Giraud
,
B.
, and
Abderrahim
,
H. A.
,
2004
, “
The Experimental Accelerator Driven System (XADS) Designs in the EURATOM 5th Framework Programme
,”
J. Nucl. Mater.
,
335
(
2
), pp.
148
155
.
5.
Abanades
,
A.
, and
Perez-Navarro
,
A.
,
2007
, “
Engineering Design Studies for the Transmutation of Nuclear Wastes With a Gas-Cooled Pebble-Bed ADS
,”
Nucl. Eng. Des.
,
237
(
3
), pp.
325
333
.
6.
Wang
,
J.
,
Tian
,
W. X.
,
Su
,
G. H.
,
Qiu
,
S. Z.
,
Xiang
,
B.
,
Zhang
,
G. S.
, and
Feng
,
K. M.
,
2013
, “
Thermal-Hydraulic and Safety Analysis for Chinese Helium-Cooled Solid Breeder TBM Cooling System
,”
Fusion Eng. Des.
,
88
(
1
), pp.
33
41
.
7.
Takenaka
,
N.
,
Nio
,
D.
,
Kiyanagi
,
Y.
,
Mishima
,
K.
,
Kawai
,
M.
, and
Furusaka
,
M.
,
2005
, “
Thermal Hydraulic Design and Decay Heat Removal of a Solid Target for a Spallation Neutron Source
,”
J. Nucl. Mater.
,
343
(
1–3
), pp.
169
177
.
8.
AN
S,
1973
, “
Decay Energy Release Rates Following Shutdown of Uranium-Fueled Thermal Reactors
,” American Nuclear Society, La Grange Park, IL, Standard No. Draft ANS-5.1/N18.6.
9.
Gao
,
Q.
,
2011
, “
Research on the Engineering Simulator for HTR-PM Based on THERMIX/BLAST and vPower
,” Ph.D. thesis, Tsinghua University, Beijing, China.
10.
Zhou
,
K. F.
,
2011
, “
Research on the Simulation Method of Thermal-Hydraulic Process in High Temperature Gas-Cooled Reactor
,” Ph.D. thesis, Tsinghua University, Beijing, China.
11.
Han
,
K. H.
,
Seo
,
K. W.
,
Hwang
,
D. H.
, and
Chang
,
S. H.
,
2006
, “
Development of a Thermal Hydraulic Analysis Code for Gas-Cooled Reactors With Annular Fuels
,”
Nucl. Eng. Des.
,
236
(2), pp.
164
178
.
12.
Wang
,
D. Y.
,
2011
, “
Simulation of High Temperature Gas Cooled Reactor's Multi-Loop System
,” Ph.D. thesis, Tsinghua University, Beijing, China.
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