Optimisation of deep burn incineration of reactor waste plutonium in a PBMR DPP-400 core

Serfontein, Dawid E.; Mulder, Eben; Reitsma, Frederik

doi:10.1016/j.nucengdes.2013.11.017

Cited by 12 publications

(5 citation statements)

References 9 publications

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“…The basis for this study is the design of the PBMR DPP-400, simulated using the VSOP 99/05 diffusion code [1,3,4], but with the standard six-pass refueling scheme replaced by an OTTO scheme.…”

Section: Simulation Methodsmentioning

confidence: 99%

“…Coupled neutronics and thermal-hydraulic simulation results for the PBMR DPP-400 for the standard uranium (U)/plutonium (Pu) fuel cycle (U/Pu(LEU)) ( Table 2), fueled with 9.6 wt% enriched Low Enriched Uranium (LEU), were reported for the VSOP 99 diffusion code by Reitsma [3] and for both VSOP-A and VSOP 99/05 by Serfontein [1] and in Serfontein et al [4]. Serfontein obtained a maximum DLOFC fuel temperature of 1577°C.…”

Section: Literature Reviewmentioning

confidence: 99%

“…The adopted safety limits from Serfontein's PhD and its follow-up studies were retained [1,4,13] and are given in Table 1.…”

Section: Safety Limitsmentioning

confidence: 99%

“…Different from the 250 MW th HTR-PM [2], the 400 MW th Pebble Bed Modular Reactor Demonstration Power Plant (PBMR DPP-400) [1,3,4] not only makes use of an external, but also of a central graphite reflector. This central reflector was introduced for the sake of increasing the power output of the reactor by pushing the fuel outwards towards the external reflector.…”

Section: Introductionmentioning

confidence: 99%

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Using thorium to reduce the maximum fuel temperatures during depressurized loss of coolant accidents in a once-through-then-out (OTTO) PBMR DPP-400 core

Pokaha

Serfontein

2017

Journal of Nuclear Science and Technology

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This article presents the results for the PBMR-DPP-400, but for a once-through-then-out (OTTO) refueling scheme. An optimization attempt of the axial and radial power profiles is reported. The main aim was to reduce the maximum depressurized loss of forced coolant (DLOFC) temperature by adding thorium to the fuel and making the fuel layout radially asymmetric by placing lower enriched fuel in the inner and higher enriched fuel in the outer fuel flow regions. These measures (1) flattened the peaks in the axial power profiles and thus suppressed the hotspots in the axial DLOFC temperature profiles and (2) 'pushed' the power radially outwards, so as to reduce the distance that the decay heat must be evacuated towards the outside of the fuel core. This resulted in a huge reduction in the maximum DLOFC temperature for the OTTO cycle from 2273 to 1811°C, which is still above the 1600°C limit but represents a remarkable result. Maximum DLOFC temperature below the 1600°C limit was obtained by reducing the power output. The results obtained and the proposed strategies for further improvement are applicable to the Chinese HTR-PM and could produce even better results in Prismatic Block Reactors such as the Japanese HTTR.

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Section: Simulation Methodsmentioning

confidence: 99%

Section: Literature Reviewmentioning

confidence: 99%

“…The adopted safety limits from Serfontein's PhD and its follow-up studies were retained [1,4,13] and are given in Table 1.…”

Section: Safety Limitsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Using thorium to reduce the maximum fuel temperatures during depressurized loss of coolant accidents in a once-through-then-out (OTTO) PBMR DPP-400 core

Pokaha

Serfontein

2017

Journal of Nuclear Science and Technology

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“…TRISO particle is a new type fuel structure, developed for high temperature reactor. The dimensions TRISO particles inspired from [17] were presented in table 1. The compositions (wt%) used in the calculations were taken as 4% 239 Pu and 6% 240 Pu for WG-Pu and 1% 238 Pu, 62% 239 Pu, 24% 240 Pu, 8% 241 Pu and 5% 242 Pu for RG-Pu [11].…”

Section: Problem Descriptionmentioning

confidence: 99%

Monte Carlo calculations of the incineration of plutonium and minor actinides of laser fusion inertial confinement fusion fission energy (LIFE) engine

Acır

Baysal

2018

Plasma Sci. Technol.

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In this paper, neutronic analysis in a laser fusion inertial confinement fusion fission energy (LIFE) engine fuelled plutonium and minor actinides using a MCNP codes was investigated. LIFE engine fuel zone contained 10 vol% TRISO particles and 90 vol% natural lithium coolant mixture. TRISO fuel compositions have Mod①: reactor grade plutonium (RG-Pu), Mod②: weapon grade plutonium (WG-Pu) and Mod③: minor actinides (MAs). Tritium breeding ratios (TBR) were computed as 1.52, 1.62 and 1.46 for Mod①, Mod② and Mod③, respectively. The operation period was computed as ∼21 years when the reference TBR>1.05 for a selfsustained reactor for all investigated cases. Blanket energy multiplication values (M) were calculated as 4.18, 4.95 and 3.75 for Mod①, Mod② and Mod③, respectively. The burnup (BU) values were obtained as ∼1230, ∼1550 and ∼1060 GWd tM-1 , respectively. As a result, the higher BU were provided with using TRISO particles for all cases in LIFE engine.

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A conceptual design for a generic heavy water research reactor to a more proliferation-resistant reactor

Khoshahval

Safdari

2018

Annals of Nuclear Energy

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Optimisation of deep burn incineration of reactor waste plutonium in a PBMR DPP-400 core

Cited by 12 publications

References 9 publications

Using thorium to reduce the maximum fuel temperatures during depressurized loss of coolant accidents in a once-through-then-out (OTTO) PBMR DPP-400 core

Using thorium to reduce the maximum fuel temperatures during depressurized loss of coolant accidents in a once-through-then-out (OTTO) PBMR DPP-400 core

Monte Carlo calculations of the incineration of plutonium and minor actinides of laser fusion inertial confinement fusion fission energy (LIFE) engine

A conceptual design for a generic heavy water research reactor to a more proliferation-resistant reactor

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