Published December 15, 2015 | Version v1
Journal article

Beam transient analyses of Accelerator Driven Subcritical Reactors based on neutron transport method

  • 1. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, Shaanxi (China)
  • 2. Nuclear and Radiation Safety Center, PO Box 8088, Beijing 100082 (China)

Description

Highlights: • A transport-based kinetics code for Accelerator Driven Subcritical Reactors is developed. • The performance of different kinetics methods adapted to the ADSR is investigated. • The impacts of neutronic parameters deteriorating with fuel depletion are investigated. - Abstract: The Accelerator Driven Subcritical Reactor (ADSR) is almost external source dominated since there is no additional reactivity control mechanism in most designs. This paper focuses on beam-induced transients with an in-house developed dynamic analysis code. The performance of different kinetics methods adapted to the ADSR is investigated, including the point kinetics approximation and space–time kinetics methods. Then, the transient responds of beam trip and beam overpower are calculated and analyzed for an ADSR design dedicated for minor actinides transmutation. The impacts of some safety-related neutronics parameters deteriorating with fuel depletion are also investigated. The results show that the power distribution varying with burnup leads to large differences in temperature responds during transients, while the impacts of kinetic parameters and feedback coefficients are not very obvious. Classification: Core physic

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2015.10.021

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2015.10.021;
PII
S0029-5493(15)00487-2;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
295
Journal Page Range
p. 489-499
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.