The Breeding Ratio with Correlation to Doubling Time and Fuel Cycle Reactivity Variation

4 fast-spectrum molten salt conceptual designs have been selected for fuel cycle performance analysis. 3D full core and 2D unit cell models have been developed to justify the possibility to use a simplified model for computational-heavy depletion simulation with truly continuous online reprocessing. Finally, 60-years depletion simulation for Molten Salt Fast Reactor (MSFR) shown lifetime breeding ratio 1.0072 and doubling time 139 years in Th/U fuel cycle.

Download Full-text

Breeding Ratio, Inventory, and Doubling time in a D-T Fusion Reactor

Nuclear Technology ◽

10.13182/nt72-a16045 ◽

1972 ◽

Vol 15 (3) ◽

pp. 470-474 ◽

Cited By ~ 17

Author(s):

W. F. Vogelsang

Keyword(s):

Doubling Time ◽

Fusion Reactor ◽

Breeding Ratio

Download Full-text

BREEDING RATIO AND DOUBLING TIME CHARACTERISTICS OF THE CLINCH RIVER BREEDER REACTOR

Advanced Reactors: Physics, Design and Economics ◽

10.1016/b978-0-08-019610-7.50059-2 ◽

1975 ◽

pp. 665-676 ◽

Cited By ~ 2

Author(s):

J.A. Lake ◽

R.A. Doncals ◽

R.W. Rathbun ◽

H.C. Robinson

Keyword(s):

Doubling Time ◽

Breeding Ratio ◽

Clinch River

Download Full-text

Self-Breeding and Radiotoxicity Analysis on Thorium-Based Molten Salt Reactors

Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors ◽

10.1115/icone21-15454 ◽

2013 ◽

Author(s):

Chun-yan Zou ◽

Jin-gen Chen ◽

Xiang-zhou Cai ◽

Cheng-gang Yu ◽

Da-zhen Jiang ◽

...

Keyword(s):

Molten Salt ◽

Nuclear Energy ◽

Fuel Cycle ◽

Molten Salt Reactor ◽

Nuclear System ◽

Energy Sustainability ◽

Waste Production ◽

Breeding Ratio ◽

Fuel Salt ◽

System Project

As one of the candidates in the Generation IV reactors program., the molten salt reactor (MSR) has the properties of online refueling and fuel salt reprocessing, MSR is especially attractive for the Thorium fuel cycle, which is very ideal for nuclear non-proliferation, radiotoxicity and nuclear energy sustainability. Therefore, the “Thorium-based Molten Salt Reactor (TMSR) nuclear system” project has been proposed as one of the “Strategic Priority Research Program” of Chinese Academy of Science (CAS). In this paper, we mainly investigated the influence on the breeding ratio and waste radiotoxicity with different reprocessing schemes. By considering the key parameters mentioned above, the aim is to choose an efficient reprocessing scheme for TMSR to reach self-breeding with Th/U fuel cycle and minimize the radioactive waste production of the molten salt.

Download Full-text

Safety Analysis of a High Breeding Fast Reactor Cooled by Supercritical-Pressure Light Water: Accidents and Abnormal Transients at Supercritical Pressure

Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security ◽

10.1115/icone22-30185 ◽

2014 ◽

Author(s):

Rui Guo ◽

Yoshiaki Oka

Keyword(s):

Fast Reactor ◽

Doubling Time ◽

Safety Analysis ◽

Supercritical Pressure ◽

Compound System ◽

System Configuration ◽

Fuel Rod ◽

Negative Reactivity ◽

Breeding Ratio ◽

Reactivity Coefficients

The high breeding core of a supercritical water cooled fast reactor has been designed with tightly packed fuel rod assemblies to obtain a high breeding ratio and negative reactivity coefficients. A high breeding capability of less than 50 years of compound system doubling time was reported by the conceptual design study of the reactor at ICONE21. The present paper describes the safety analysis of the reactor for accidents and abnormal transients at supercritical pressure. The safety principle, safety system configuration and types of the abnormal transients and accidents are the same as those of the Super FR [1]. Safety criteria such as cladding temperature, pressure and fuel enthalpy are similar to those of Super FR. Results indicate that all safety criteria are satisfied.

Download Full-text

Definitions of Breeding Ratio and Doubling Time

Nuclear Technology ◽

10.13182/nt74-a31387 ◽

1974 ◽

Vol 21 (3) ◽

pp. 158-164 ◽

Cited By ~ 11

Author(s):

Harvey L. Wyckoff ◽

Paul Greebler

Keyword(s):

Doubling Time ◽

Breeding Ratio

Download Full-text

Study on Neutronics and Fuel Cycle of Fusion-Fission Hybrid Reactor

18th International Conference on Nuclear Engineering: Volume 6 ◽

10.1115/icone18-30048 ◽

2010 ◽

Author(s):

Hong Xu ◽

Yongwei Yang ◽

Zhiwei Zhou

Keyword(s):

Fuel Cycle ◽

Hybrid Reactor ◽

Code System ◽

Tritium Breeding ◽

Fusion Plasma ◽

Plasma Parameters ◽

Realistic Condition ◽

Breeding Material ◽

Breeding Ratio ◽

Zr Alloy

A conceptual design on neutronics of Fusion-Fission Hybrid Reactor (FFHR) blanket is presented in this paper. The code system COUPLE2.0, which couples the codes MCNP and ORIGEN2 is uesd to simulate the depletion of nucleus for FFHR blanket. By comparing different kinds of coolant, fission fuel and tritium breeding material etc, light water was selected as the coolant, the U-Zr alloy as fuel and Li4SiO4 as tritium breeding material. The volumetric ratio of showed that under that the coolant to fuel is approximately 2.0. The tritium breeding ratio (TBR) must be larger than 1.0, the keff and the energy multiplication factor of the blanket are both comparatively high, so that high breeding ratio of fuel can obtained under realistic condition of fusion plasma parameters.

Download Full-text