Effect of coolant channel width on group constants and multiplication factor of research reactors using MTR type low enriched uranium fuel

Since the 1970's, global efforts have been going on to replace the high-enriched (>90% 235U), low-density UAlx research reactor fuel with high-density, low enriched (<20% 235U) replacements. This search is driven by the attempt to reduce the civil use of high-enriched material because of proliferation risks and terrorist threats. American initiatives, such as the Global Threat Reduction Initiative (GTRI) and the Reduced Enrichment for Research and Test Reactors (RERTR) program have triggered the development of reliable low-enriched fuel types for these reactors, which can replace the high enriched ones without loss of performance. Most success has presently been obtained with U3Si2 dispersion fuel, which is currently used in many research reactors in the world. However, efforts to search for a replacement with even higher density, which will also allow the conversion of some high flux research reactors that currently cannot change to U3Si2 (eg. BR2 in Belgium), have continued and are for the moment mainly directed towards the U(Mo) alloy fuel (7-10 w% Mo). This paper provides an overview of the past efforts and presents the current status of the U(Mo) development.

Download Full-text

From High-Enriched to Low-Enriched Uranium Fuel in Research Reactors

Revue Générale Nucléaire ◽

10.1051/rgn/20106082 ◽

2010 ◽

pp. 82-89

Author(s):

S. Van Den Berghe ◽

A. Leenaers ◽

E. Koonen ◽

F. Moons ◽

L. Sannen

Keyword(s):

Research Reactors ◽

Uranium Fuel ◽

Enriched Uranium

Download Full-text

High-density, low-enriched uranium fuel for nuclear research reactors

JOM ◽

10.1007/s11837-003-0031-0 ◽

2003 ◽

Vol 55 (9) ◽

pp. 55-58 ◽

Cited By ~ 45

Author(s):

D. D. Keiser ◽

S. L. Hayes ◽

M. K. Meyer ◽

C. R. Clark

Keyword(s):

Nuclear Research ◽

High Density ◽

Research Reactors ◽

Uranium Fuel ◽

Enriched Uranium

Download Full-text

Status of the Low Enriched Uranium Fuel Development for High Performance Research Reactors

Advances in Science and Technology ◽

10.4028/www.scientific.net/ast.94.43 ◽

2014 ◽

Vol 94 ◽

pp. 43-54 ◽

Cited By ~ 1

Author(s):

Leo Sannen ◽

Sven van den Berghe ◽

Ann Leenaers

Keyword(s):

High Performance ◽

Alternative Fuels ◽

Volume Density ◽

Lessons Learned ◽

Research Reactors ◽

Dispersion Fuel ◽

Uranium Fuel ◽

Low Volume ◽

Enriched Uranium ◽

Performance Research

Historically, uranium enriched to >90% 235U has been used for many peaceful applications requiring high fission densities such as driver fuels for research reactors. However, the use of high-enriched uranium or HEU (all enrichments >20% 235U are considered HEU) for civil applications, is considered a proliferation concern. Since the 1970's, efforts are being devoted to the conversion of research reactors operating on HEU to alternative fuels using uranium with enrichment below 20% or LEU. These efforts imply the development of high-density LEU fuels to replace the low volume-density (mostly) UAlx based HEU fuels. The paper updates the present status of these developments focusing on the UMo dispersion fuel. It aims to provide an overview of the knowledge generated and the lessons learned in roughly 15 years of UMo dispersion fuel R&D in Europe through irradiation experiments and post-irradiation examinations (PIE).

Download Full-text

Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly

Journal of Nuclear Science and Technology ◽

10.1080/00223131.2021.2017371 ◽

2022 ◽

pp. 1-9

Author(s):

Cheol Ho Pyeon ◽

Kota Morioka

Keyword(s):

Uncertainty Quantification ◽

Critical Assembly ◽

Light Water ◽

Uranium Fuel ◽

Enriched Uranium

Download Full-text

The Current Status of Converting the University of Missouri Research Reactor from Highly Enriched Uranium to Low-Enriched Uranium Fuel

10.13182/t123-33457 ◽

2020 ◽

Author(s):

A. Moisseytsev ◽

D. Yoon ◽

E. Feldman ◽

J. Stillman ◽

K. Kutikkad ◽

...

Keyword(s):

Research Reactor ◽

Current Status ◽

University Of Missouri ◽

Uranium Fuel ◽

Enriched Uranium ◽

The University

Download Full-text

Preliminary Core Design and Optimization Analysis of Travelling Wave Reactor

Advanced Materials Research ◽

10.4028/www.scientific.net/amr.1070-1072.357 ◽

2014 ◽

Vol 1070-1072 ◽

pp. 357-360

Author(s):

Dao Xiang Shen ◽

Yao Li Zhang ◽

Qi Xun Guo

Keyword(s):

Monte Carlo ◽

Rational Design ◽

Nuclear Reactor ◽

Reactor Core ◽

Travelling Wave ◽

Optimization Analysis ◽

Design And Optimization ◽

Uranium Fuel ◽

Enriched Uranium ◽

Ignition Zone

A travelling wave reactor (TWR) is an advanced nuclear reactor which is capable of running for decades given only depleted uranium fuel, it is considered one of the most promising solutions for nonproliferation. A preliminary core design was proposed in this paper. The calculation was performed by Monte Carlo method. The burning mechanism of the reactor core design was studied. Optimization on the ignition zone was performed to reduce the amount of enriched uranium initially deployed. The results showed that the preliminary core design was feasible. The optimization analysis showed that the amount of enriched uranium could be reduced under rational design.

Download Full-text