0
Technical Brief

Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System

[+] Author and Article Information
Tianji Peng

Institute of Modern Physics,
Chinese Academy of Sciences,
Lanzhou 730000, China
e-mail: pengtianji@163.com

Zhiwei Zhou

Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China

1Corresponding author.

Manuscript received April 14, 2016; final manuscript received October 18, 2016; published online March 1, 2017. Assoc. Editor: Yanping Huang.

ASME J of Nuclear Rad Sci 3(2), 024502 (Mar 01, 2017) (6 pages) Paper No: NERS-16-1037; doi: 10.1115/1.4035333 History: Received April 14, 2016; Revised October 18, 2016

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.

Copyright © 2017 by ASME
Your Session has timed out. Please sign back in to continue.

References

Figures

Grahic Jump Location
Fig. 1

Configuration of reactor core. 1—Fuel zone, 2—side replaceable reflector, 3—top replaceable reflector, 4—bottom replaceable reflector, 5—hot plenum and core support, 6—side permanent reflector, 7—side shielding block, 8—riser channel, 9—reactor pressure vessel, 10—cavity cooling panels, 11—air, 12—concrete, 13—He inlet, 14—He outlet, 15—lower plenum, 16—upper plenum, 17—target tube, 18—proton beam, 19—target, and 20—header.

Grahic Jump Location
Fig. 2

Geometry of target

Grahic Jump Location
Fig. 3

Power density distribution of target (W cm−3)

Grahic Jump Location
Fig. 4

Power distribution of core

Grahic Jump Location
Fig. 5

Decay heat of target and core

Grahic Jump Location
Fig. 6

Heat transfer mechanisms of ADS

Grahic Jump Location
Fig. 7

Target grids (partial): (a) solid, (b) fluid, and (c) connection between target grids

Grahic Jump Location
Fig. 8

Reactor nodes of solid domain: (a) top view and (b) side view

Grahic Jump Location
Fig. 9

The flow of calculation procedure

Grahic Jump Location
Fig. 10

Temperature comparison of target solid: (a) temperature on line 1 (x = 114 mm and z = 70 mm) and (b) temperature on line 2 (x = 114 mm and y = 114 mm)

Grahic Jump Location
Fig. 11

RELAP5–TRCAP coupling model

Grahic Jump Location
Fig. 12

Equivalent component of target/core

Grahic Jump Location
Fig. 13

RELAP5–TRCAP coupling calculation method

Grahic Jump Location
Fig. 14

Blocks temperature distribution (center section) (K)

Grahic Jump Location
Fig. 15

Target temperature distribution of solid (K)

Grahic Jump Location
Fig. 16

Temperature response of the target (K) (x = 114 mm and z = 70 mm)

Grahic Jump Location
Fig. 17

Temperature response of target and core

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In