The Critical HTGR Test Facility KAHTER–An Experimental Program for Verification of Theoretical Models, Codes, and Nuclear Data Bases

Drüke, V.; Filges, D.

doi:10.13182/nse87-a23493

Cited by 6 publications

(2 citation statements)

References 2 publications

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“…Critical PBR facilities have been built in Germany [16], Switzerland [3], and Russia [17]. Japan began fuel and materials testing for its HTGR program in 1976 and the 30 MWt High Temperature Test Reactor (HTTR) began operation in 1998 [18].…”

Section: Summary Of High-temperature Reactor Design Effortsmentioning

confidence: 99%

Advanced Core Design And Fuel Management For Pebble-Bed Reactors

Gougar¹,

Ougouag²,

Terry³

2004

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A method for designing and optimizing recirculating pebble-bed reactor cores is presented. At the heart of the method is a new reactor physics computer code, PEBBED, which accurately and efficiently computes the neutronic and material properties of the asymptotic (equilibrium) fuel cycle. This core state is shown to be unique for a given core geometry, power level, discharge burnup, and fuel circulation policy. Fuel circulation in the pebble-bed can be described in terms of a few well-defined parameters and expressed as a recirculation matrix. The implementation of a few heat-transfer relations suitable for high-temperature gas-cooled reactors allows for the rapid estimation of thermal properties critical for safe operation. Thus, modeling and design optimization of a given pebble-bed core can be performed quickly and efficiently via the manipulation of a limited number key parameters. Automation of the optimization process is achieved by manipulation of these parameters using a genetic algorithm. The end result is an economical, passively safe, proliferation-resistant nuclear power plant. iv

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Section: Summary Of High-temperature Reactor Design Effortsmentioning

confidence: 99%

Advanced Core Design And Fuel Management For Pebble-Bed Reactors

Gougar¹,

Ougouag²,

Terry³

2004

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“…However, looking deeper into the development of the programme, the importance of zero power experiments is even more highlighted due to the decision for the demand of a zero-power facility as basis to provide more hands on testing, leading to the KAHTER facility in 1973 [3]. The developers of the HTR programme confirmed that zero power tests have been essential for the optimization of the system and the confirmation of theoretical models [4]. Nowadays, scientists claim that it is possible to design a new reactor based on modelling and simulation only, which may be true for a known technology like light water reactors with a very broad validation base and a wide variety of specially developed codes.…”

Section: Introductionmentioning

confidence: 99%

On the Dimensions Required for a Molten Salt Zero Power Reactor Operating on Chloride Salts

et al. 2021

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Molten salt reactors have gained substantial interest in the last years due to their flexibility and their potential for simplified closed fuel cycle operation for massive expansion in low-carbon electricity production, which will be required for a future net-zero society. The importance of a zero-power reactor for the process of developing a new, innovative rector concept, such as that required for the molten salt fast reactor based on iMAGINE technology, which operates directly on spent nuclear fuel, is described here. It is based on historical developments as well as the current demand for experimental results and key factors that are relevant to the success of the next step in the development process of all innovative reactor types. In the systematic modelling and simulation of a zero-power molten salt reactor, the radius and the feedback effects are studied for a eutectic based system, while a heavy metal rich chloride-based system are studied depending on the uranium enrichment accompanied with the effects on neutron flux spectrum and spatial distribution. These results are used to support the relevant decision for the narrowing down of the configurations supported by considerations on cost and proliferation for the follow up 3-D analysis. The results provide for the first time a systematic modelling and simulation approach for a new reactor physics experiment for an advanced technology. The expected core volumes for these configurations have been studied using multi-group and continuous energy Monte-Carlo simulations identifying the 35% enriched systems as the most attractive. This finally leads to the choice of heavy metal rich compositions with 35% enrichment as the reference system for future studies of the next steps in the zero power reactor investigation. An alternative could be the eutectic system in the case the increased core diameter is manageable. The inter-comparison of the different applied codes and approaches available in the SCALE package has delivered a very good agreement between the results, creating trust into the developed and used models and methods.

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