Eleonora Bomboni

Nicola Cerullo

Guglielmo Lomonaco

Erratum for &#8220;Assessment of LWR-HTR-GCFR Integrated Cycle&#8221;

Jan Leen Kloosterman

Jim Kuijper

Colin Mitchell

Innovative Gas-Cooled Reactors

In the recent past the so-called GCFR has been again a subject of study by the international scientific community. This type of reactors, although still in a preliminary stage of development, is a very interesting perspective because combines the positive characteristics common to all the fast reactors with those of the reactors cooled by helium. Up to now, almost all the analyses on the GCFR thermodynamic aspects have been performed starting from a “global” point of view: generally the core has been modelled as a porous medium and only the global parameters have been taken into account. The local effects have been included in <i>adhoc</i> corrective peak factors. The analyses carried out in the present research will be devoted to the characterization of the local effects, on a microscopic scale. In order to have reliable “global” nuclear and thermal-fluid-dynamic data, the performed analyses will be based on simulations previously performed using the RELAP5-3D code, assuming as input parameters the ETDR core ones. For each considered case, the variation ranges of the evaluated parameters have been estimated on the basis of the “best” and the “worst” cases. To summarize the obtained results, even in transient conditions, the variations of the considered input parameters are less significant for the local output values if compared to those due to the assumed packing factor. As a consequence, in a more general core calculation, the obtained local temperature (and velocity) values will have to be corrected by a proper factor that would have to take into account the results of this research.

G. Lomonaco

W. Grassi

N. Cerullo

The Influence of the Packing Factor on the Fuel Temperature Hot
Spots in a Particle-Bed GCFR

Gas-cooled fast reactor (GFR) research is directed towards fulfilling the ambitious goals of Generation IV (Gen IV), that is, to develop a safe, sustainable, reliable, proliferation-resistant and economic nuclear energy system. The research is directed towards developing the GFR as an economic electricity generator, with good safety and sustainability characteristics. Fast reactors maximise the usefulness of uranium resources by breeding plutonium and can contribute to minimising both the quantity and radiotoxicity nuclear waste by actinide transmutation in a closed fuel cycle. Transmutation is particularly effective in the GFR core owing to its inherently hard neutron spectrum. Further, GFR is suitable for hydrogen production and process heat applications through its high core outlet temperature. As such GFR can inherit the non-electricity applications that will be developed for thermal high temperature reactors in a sustainable manner. The Euratom organisation provides a route by which researchers in all European states, and other non-European affiliates, can contribute to the Gen IV GFR system. This paper summarises the achievements of Euratom's research into the GFR system, starting with the 5th Framework programme (FP5) GCFR project in 2000, through FP6 (2005 to 2009) and looking ahead to the proposed activities within the 7th Framework Programme (FP7).

Richard Stainsby

Karen Peers

Christian Poette

Konstantin Mikityuk

Joe Somers

Gas Cooled Fast Reactor Research and Development in the European Union

In order to guarantee a sustainable supply of future energy demand
without compromising the environment, some actions for a
substantial reduction of <svg style="vertical-align:-3.13504pt;width:27.799999px;" id="M1" height="14.6" version="1.1" viewBox="0 0 27.799999 14.6" width="27.799999"  xmlns="http://www.w3.org/2000/svg">
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			</text>

		</g>
	</g>
</svg> emissions are nowadays deeply analysed. One of them is
the improvement of the nuclear energy use. In this framework,
innovative gas-cooled reactors (both thermal and fast) seem to be
very attractive from the electricity production point of view and
for the potential industrial use along the high temperature
processes (e.g., <svg style="vertical-align:-3.13504pt;width:17.5px;" id="M2" height="14.375" version="1.1" viewBox="0 0 17.5 14.375" width="17.5"  xmlns="http://www.w3.org/2000/svg">
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		</g>
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</svg> production by steam reforming or I-S process). This
work focuses on a preliminary (and conservative) evaluation of
possible advantages that a symbiotic cycle (EPR-PBMR-GCFR) could
entail, with special regard to the reduction of the HLW inventory
and the optimization of the exploitation of the fuel resources. 
The comparison between the symbiotic cycle chosen and the
reference one (once-through scenario, i.e., EPR-SNF directly
disposed) shows a reduction of the time needed to reach a fixed
reference level from
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</svg>1550 years
(comparable with typical human times and for this reason more
acceptable by the public opinion). In addition, this cycle enables
to have a more efficient use of resources involved: the total
electric energy produced becomes equal to
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</svg>630&#x2009;TWh/year
(instead of only
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</svg>530&#x2009;TWh/year
using only EPR) without consuming additional raw materials.

Barbara Vezzoni

Giuseppe Forasassi

Emil Fridman

Vincenzo Romanello

Eugene Shwageraus

Preliminary Evaluation of a Nuclear Scenario Involving Innovative Gas Cooled Reactors

Nowadays nuclear is the only greenhouse-free source that can appreciably respond to the increasing worldwide energy demand. The use of Thorium in the nuclear energy production may offer some advantages to accomplish this task. Extensive R&amp;D on the thorium fuel cycle has been conducted in many countries around the world. Starting from the current nuclear waste policy, the EU-PUMA project focuses on the potential benefits of using the HTR core as a Pu/MA transmuter. In this paper the following aspects have been analysed: (1) the state-of-the-art of the studies on the use of Th in different reactors, (2) the use of Th in HTRs, with a particular emphasis on Th-Pu fuel cycles, (3) an original assessment of Th-Pu fuel cycles in HTR. Some aspects related to Thorium exploitation were outlined, particularly its suitability for working in pebble-bed HTR in a Th-Pu fuel cycle. The influence of the Th/Pu weight fraction at BOC in a typical HTR pebble was analysed as far as the reactivity trend versus burn-up, the energy produced per Pu mass, and the Pu isotopic composition at EOC are concerned. Although deeper investigations need to be performed in order to draw final conclusions, it is possible to state that some optimized Th percentage in the initial Pu/Th fuel could be suggested on the basis of the aim we are trying to reach.

Guido Mazzini

The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles


Preliminary analyses already performed showed that innovative GCRs, both thermal and fast, are very promising candidate to reach the Gen-IV sustainability goal. The integrated LWR-HTR-GCFR basically aims at closing the current nuclear fuel cycle: in principle, thanks to the unique characteristics of Helium coolant reactors, LWR SNF along with DU become valuable material to produce energy. Additionally, burning HMs of LWR SNF means not only a drastic reduction in the <svg style="vertical-align:-0.17554pt;width:25.4px;" id="M1" height="12.925" version="1.1" viewBox="0 0 25.4 12.925" width="25.4"  xmlns="http://www.w3.org/2000/svg">
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</svg> demand but also a remarkable decrease in the long-term radiotoxic component of nuclear waste to be geologically stored. This paper focuses on the analyses of the LWR-HTR-GCFR cycle performed by the University of Pisa in the frame of the EU PUMA project (6th FP). Starting from a brief outline of the main characteristics of HTR and GCFR concepts and of the advantages of linking LWR, HTR and GCFR in a symbiotic way, this paper shows the integrated cycle involving a typical LWR (1000&#x2009;<svg style="vertical-align:-3.22281pt;width:34.25px;" id="M2" height="14.4875" version="1.1" viewBox="0 0 34.25 14.4875" width="34.25"  xmlns="http://www.w3.org/2000/svg">
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</svg>), a PBMR (400&#x2009;<svg style="vertical-align:-3.22281pt;width:38px;" id="M3" height="14.4875" version="1.1" viewBox="0 0 38 14.4875" width="38"  xmlns="http://www.w3.org/2000/svg">
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</svg>) and a GCFR-&#x201C;E&#x201D; (2400&#x2009;<svg style="vertical-align:-3.22281pt;width:38px;" id="M4" height="14.4875" version="1.1" viewBox="0 0 38 14.4875" width="38"  xmlns="http://www.w3.org/2000/svg">
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</svg>). Additionally, a brief overview of the main technological constraints concerning (Pu+MA)-based advanced fuels is given, in order to explain and justify the choices made in the framework of the considered cycle. Thereafter, calculations performed and results obtained are described. 


Assessment of LWR-HTR-GCFR Integrated Cycle

Development of HTRs requires the performance of a thorough safety study, which includes accident analyses. Confinement building performance is a key element of the system since the behaviour of aerosol and attached fission products within the building is of an utmost relevance in terms of the potential source term to the environment. This paper explores the available simulation capabilities (ASTEC and CONTAIN codes) and illustrates the performance of a postulated HTR vented confinement under prototypical accident conditions by a scoping study based on two accident sequences characterized by Helium Pressure Boundary breaches, a small and a large break. The results obtained indicate that both codes predict very similar thermal-hydraulic responses of the confinement both in magnitude and timing. As for the aerosol behaviour, both codes predict that most of the inventory coming into the confinement is eventually depleted on the walls and only about 1&#37; of the aerosol dust is released to the environment. The crosscomparison of codes states that largest differences are in the intercompartmental flows and the in-compartment gas composition.

Joan Fontanet

Luis E. Herranz

Alastair Ramlakan

Lolan Naicker

Modelling of HTR Confinement Behaviour during Accidents Involving Breach of the Helium Pressure Boundary

The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a GEN IV direct-cycle gas-cooled fast reactor (GFR) which is based on the technology developments of the HTRs. Given the different criteria and design characteristics of the GFR, an approach different from that taken for the HTRs for passive DHR would have to be explored. Different design options based on maintaining core flow were evaluated by performing transient analysis of a depressurization accident using the system code RELAP5-3D. The study also reviewed the conceptual design of autonomous systems for shutdown 
                  decay heat removal and recommends that future work in this area should be focused on the potential for Brayton cycle DHRs.

Lap-Yan Cheng

Thomas Y. C. Wei

Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors

A review is given of developments in the area of Gas-Cooled Fast Reactors (GCFR) in the period from roughly 1960 until 1980. During that period, the GCFR concept was expected to increase the breeding gain, the thermal efficiency of a nuclear power plant, and alleviate some of the problems associated with liquid metal coolants. During this period, the GCFR concept was found to be more challenging than liquid-metal-cooled reactors, and none were ever constructed. In the second part of the paper, we provide an overview of the investigations on GCFR since the year 2000, when the Generation IV Initiative rekindled interest in this reactor type. The new GCFR concepts focus primarily on sustainable nuclear power, with very efficient resource use, minimum waste, and a very strong focus on (passive) safety. An overview is presented of the main design characteristics of these Gen IV GCFRs, and a literature list is provided to guide the interested reader towards more detailed publications.

W. F. G. van Rooijen

Gas-Cooled Fast Reactor: A Historical Overview and Future Outlook

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<p><em>Science and Technology of Nuclear Installations</em> publishes research on issues related to the nuclear industry, particularly the installations of nuclear technology, and aims to promote development in the area of nuclear sciences and technologies.</p>


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Science and Technology of Nuclear Installations

Innovative Gas-Cooled Reactors

Innovative Gas-Cooled Reactors

Articles

Erratum for “Assessment of LWR-HTR-GCFR Integrated Cycle”

Innovative Gas-Cooled Reactors

The Influence of the Packing Factor on the Fuel Temperature Hot Spots in a Particle-Bed GCFR

Gas Cooled Fast Reactor Research and Development in the European Union

Preliminary Evaluation of a Nuclear Scenario Involving Innovative Gas Cooled Reactors

The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles

Assessment of LWR-HTR-GCFR Integrated Cycle

Modelling of HTR Confinement Behaviour during Accidents Involving Breach of the Helium Pressure Boundary

Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors

Gas-Cooled Fast Reactor: A Historical Overview and Future Outlook