scholarly journals MINIMIZED FUEL CYCLE COST FOR A SIMULATED HEAVY WATER REACTOR. PART I.

1965 ◽  
Author(s):  
D.E. Deonigi ◽  
P.A. Horton ◽  
A.F. McConiga
Keyword(s):  
Heavy Water ◽  
Fuel Cycle ◽  
Water Reactor ◽  
Heavy Water Reactor

scholarly journals ON THE USE OF A CENTRAL THORIUM FUEL ELEMENT IN PRESSURE-TUBE HEAVY-WATER REACTOR FUEL BUNDLES

2018 ◽  
Vol 7 (2) ◽  
pp. 147-155 ◽  
Author(s):  
Michael McDonald ◽  
Megan Moore ◽  
Dan Wojtaszek ◽  
Nicholas Chornoboy ◽  
Geoffrey Edwards
Keyword(s):  
Fuel Element ◽  
Heavy Water ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Pressure Tube ◽  
Slight Reduction ◽  
Energy Potential ◽  
Thorium Dioxide ◽  
Water Reactor ◽  
Heavy Water Reactor

An incremental approach to introducing thorium to the conventional pressure-tube heavy-water reactor natural uranium fuel cycle is investigated. The approach involves the replacement of the centre fuel element of the bundle with an element of thorium dioxide. Increasing the operating margin of a key safety parameter, the coolant void reactivity, is a prime motivating factor. The analyses showed that the simple use of a single pin of thorium is unlikely to be economically advantageous due to a large burnup penalty and increased fuel costs. However, a slight reduction in the void reactivity is observed, and this approach does allow the exploitation of the energy potential available in thorium as an alternative nuclear fuel resource through the development of a U-233 resource. This bundle concept may also be advantageous from a fuel disposal point of view, as the fuel requires less time in storage before emplacement in a deep geological repository.

A Case Study for INPRO Methodology Based on Indian Advanced Heavy Water Reactor

2004 ◽  
Author(s):  
K. Anantharaman ◽  
D. Saha ◽  
R. K. Sinha
Keyword(s):  
Heavy Water ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Energy System ◽  
Water Reactor ◽  
Fuel Cycles ◽  
Heavy Water Reactor ◽  
Tube Type ◽  
Near Future

Under Phase 1A of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) a methodology (INPRO methodology) has been developed which can be used to evaluate a given energy system or a component of such a system on a national and/or global basis. The INPRO study can be used for assessing the potential of the innovative reactor in terms of economics, sustainability and environment, safety, waste management, proliferation resistance and cross cutting issues. India, a participant in INPRO program, is engaged in a case study applying INPRO methodology based on Advanced Heavy Water Reactor (AHWR). AHWR is a 300 MWe, boiling light water cooled, heavy water moderated and vertical pressure tube type reactor. Thorium utilization is very essential for Indian nuclear power program considering the indigenous resource availability. The AHWR is designed to produce most of its power from thorium, aided by a small input of plutonium-based fuel. The features of AHWR are described in the paper. The case study covers the fuel cycle, to be followed in the near future, for AHWR. The paper deals with initial observations of the case study with regard to fuel cycle issues.

Pressurized Heavy Water Reactor Technology: Its Relevance Today

2017 ◽  
Vol 3 (2) ◽  
Author(s):  
A. K. Nayak ◽  
S. Banerjee
Keyword(s):  
Heavy Water ◽  
Fuel Cycle ◽  
Substantial Improvement ◽  
Natural Uranium ◽  
Excellent Performance ◽  
Water Reactor ◽  
Reactor Technology ◽  
Mox Fuel ◽  
Heavy Water Reactor ◽  
Water Reactors

The pressurized heavy water reactor (PHWR) technology was conceived in Canada and has moved to several nations for commercial production of electricity. Currently, 49 power reactors operate with PHWR technology producing nearly 25 GWe. The technology is flexible for adopting different fuel cycle options which include natural uranium, different mixed oxide (MOX) fuel, and thorium. The technology has made substantial improvement in materials, construction, and safety since its inception. PHWRs have demonstrated excellent performance historically. Their safety statistics are excellent. Indian PHWRs also have shown economic competitiveness even in small sizes, thus providing an ideal design for new entrants. While the technology features of PHWRs are available even in textbooks, the objective of this paper is to highlight the historical development and salient features, and innovations for further improvement in operation, safety and economics. Thus, this paper shall serve as a curtain raiser for the special issue “Pressurized Heavy Water Reactors (PHWRs) Safety: Post Fukushima.”

Effect of Inlet Configuration on Moderator Velocity and Temperature Distribution Inside the Calandria of a Heavy Water Reactor

2008 ◽  
Author(s):  
Abhijeet Mohan Vaidya ◽  
Naresh Kumar Maheshwari ◽  
Pallippattu Krishnan Vijayan ◽  
Dilip Saha ◽  
Ratan Kumar Sinha
Keyword(s):  
Temperature Distribution ◽  
Impact Velocity ◽  
Heavy Water ◽  
Computational Study ◽  
Water Reactor ◽  
Heavy Water Reactor ◽  
The Impact

Computational study of the moderator flow in calandria vessel of a heavy water reactor is carried out for three different inlet nozzle configurations. For the computations, PHOENICS CFD code is used. The flow and temperature distribution for all the configurations are determined. The impact of moderator inlet jets on adjacent calandria tubes is studied. Based on these studies, it is found that the inlet nozzles can be designed in such a way that it can keep the impact velocity on calandria tubes within limit while keeping maximum moderator temperature well below its boiling limit.

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