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.”

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.

Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India

2017 ◽  
Vol 3 (2) ◽  
Author(s):  
S. Banerjee ◽  
H. P. Gupta
Keyword(s):  
Heavy Water ◽  
Fuel Cycle ◽  
High Capacity ◽  
Natural Uranium ◽  
Closed Fuel Cycle ◽  
Uranium Fuel ◽  
Present Generation ◽  
Heavy Water Reactor ◽  
Water Reactors ◽  
Safety Features

The technology of pressurized heavy water reactors (PHWRs) which was developed with prime objectives of using natural uranium fuel, implementing on power fuelling, utilizing mined uranium most effectively, and achieving excellent neutron economy has demonstrated impressive performance in terms of high capacity factors and an impeccable safety record. The safety features and several technology advancements evolved over the years in which Indian contributions that are considerable are briefly discussed in the first part of the paper. Unique features of PHWR such as flexibility of fuel management, distribution of pressure boundaries in multiple pressure tubes (PTs), and a large inventory of coolant-moderator heat sink in close proximity of the core provide inherent safety and fuelling options to these reactors. PHWRs, in India have demonstrated to have the advantage of lower capital cost per megawatt even in small size reactors. Low burn up associated with natural uranium fuel, higher level of tritium in the heavy water coolant, and a slightly positive coolant void coefficient in present generation PHWRs have all been addressed in the design of advanced heavy water reactor (AHWR). The merit of adopting closed fuel cycle with partitioning of minor actinides in reducing the burden of radio-toxicity of nuclear waste and of deploying light water reactors (LWRs) in tandem with PHWRs in the evolving nuclear fuel cycle in India are also discussed.

Sensitivity Degradation Characteristics of Incore Neutron Detector for Heavy Water Reactor, Fugen NPP

2002 ◽  
Author(s):  
Tsuyoshi Okawa ◽  
Naoyuki Yomori
Keyword(s):  
Thermal Neutron ◽  
Heavy Water ◽  
Power Distribution ◽  
Neutron Detector ◽  
Nuclear Power ◽  
Operating Cost ◽  
Water Reactor ◽  
Mox Fuel ◽  
Heavy Water Reactor ◽  
Test Reactor

Fugen nuclear power plant is a 165MWe, heavy water-moderated, boiling light water-cooled, pressure tube-type reactor developed by JNC, which is the world’s first thermal neutron power reactor to utilize mainly Uranium and Plutonium mixed oxide (MOX) fuel. Fugen has been loaded a total of 726 MOX fuel assemblies since the initial core in 1978. Each incore neutron detector assembly of Fugen composed of four Local Power Monitors (LPM) is located at sixteen positions in the area of heavy water moderator in the core and monitors its power distribution during operation. The thermal neutron flux of Fugen is relatively higher than that of Boiling Water Reactor (BWR), therefore LPM, which is comprised of a fission chamber, degrades more quickly than that of BWR. An Improved Long-life LPM (LLPM) pasted inner surface wall of the chamber with 234U/235U at a ratio of 4 to 1 had been developed through the irradiation test at Japan Material Test Reactor (JMTR). The 234U is converted to 235U with absorption of neutron, and compensates the consumption of 235U. LPM has been loaded to the initial core of Fugen since 1978. JNC had evaluated its sensitivity degradation characteristics through the accumulated irradiation data and the parametric survey for 234σa and 235σa. Based on the experience of evaluation for sensitivity degradation, JNC has applied shuffling operation of LPM assemblies during an annual inspection outage to reduce the operating cost. This operation realizes the reduction of replacing number of LPM assemblies and volume of radioactive waste. This paper describes the sensitivity degradation characteristics of incore neutron detector and the degradation evaluation methods established in Fugen.

Future Fuel Cycles: A Global Perspective

2008 ◽  
Author(s):  
Romney B. Duffey
Keyword(s):  
Heavy Water ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
Global Perspective ◽  
Nuclear Power Reactor ◽  
Energy Futures ◽  
Fuel Cycles ◽  
Reactor Technology ◽  
Heavy Water Reactor ◽  
Enriched Uranium

Nuclear energy must be made available, freely and readily, to help meet world energy needs. The perspective offered here is a model for others to consider, adopting and adapting using whatever elements fit their own strategies and needs. The underlying philosophy is to retain flexibility in the reactor development, deployment and fuel cycle, while ensuring the principle that customer, energy market, safety, non-proliferation and sustainability needs are all addressed. Canada is the world’s largest exporter of uranium, providing about one-third of the world supply for nuclear power reactors. Canada’s Atomic Energy of Canada Limited (AECL) has developed a unique world-class nuclear power reactor technology — the CANDU® reactor based on the Pressure Tube Reactor (PTR) concept, moderated by heavy water (D2O), also sometimes called the Pressurized Heavy Water reactor or PHWR. With expectations of significant expansion in nuclear power programs worldwide and the resultant concerns about uranium availability and price, there is a growing desire to improve resource utilization by extracting more energy from each tonne of mined fissionable material. Attention is therefore being increasingly focused on fuel cycles that are more energy efficient, reduce waste streams and ensure sustainable futures. There are also many compelling reasons to utilize advanced fuel cycles in PTR (CANDU-type) thermal spectrum reactors. Because of its inherent technical characteristics, PTRs have a great deal of fuel cycle flexibility. The combination of relatively high neutron efficiency (provided by heavy water moderation and careful selection of core materials), on-line fuelling capability and simple fuel bundle design mean that PTR reactors can use not only natural and enriched uranium, but also a wide variety of other fuels including thorium-based fuels and those resulting from the recycle of irradiated fuel. In addition, the PTR can be optimized as a very effective “intermediate burner” to provide efficient fuel cycles that remove residual minor actinides. This inherent fuel cycle flexibility offers many technical, resource and sustainability, and economic advantages over other reactor technologies and is the subject of this paper. The design evolution and intent is to be consistent with improved or enhanced safety, licensing and operating limits and global proliferation concerns, and sustainable energy futures.

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

General Survey of a Natural Uranium Heavy Water Reactor

1956 ◽  
Vol 59 (449) ◽  
pp. 500-506
Author(s):  
Masutaro SHIBATA ◽  
Masakichi MATSUMOTO ◽  
Shoichi HIRAYAMA
Keyword(s):  
Heavy Water ◽  
Natural Uranium ◽  
General Survey ◽  
Water Reactor ◽  
Heavy Water Reactor

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.

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