Analysis of Neutronics and Thermal-Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)

The main goals of fuel development for pressurized water reactor are effectiveness and economic efficiency. Both requirements can be achieved by gradual increase of discharged fuel burn-up and prolongation of fuel cycle. The mentioned effects can be reached by optimisation of fuel assembly profiling, fuel enrichment raise, and by parasitic absorption reduction. These methods were used in VVER-440 fuel assembly optimisation, described in this paper. Fuel pin configurations with enrichment limit 5 % and also enlarged one up to 5.95 % U235 were designed. Reduction of parasitic absorption was limited by carcass frame of the assembly. Basic characteristics of the best assembly proposals are presented and effects on equilibrium fuel cycle of VVER-440 reactor are characterized.

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Analysis of Pressurized Water Reactor Fuel Pin Length Changes

Zirconium in the Nuclear Industry ◽

10.1520/stp36681s ◽

2009 ◽

pp. 202-202-11

Author(s):

JE Harbottle ◽

RM Cornell

Keyword(s):

Reactor Fuel ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Fuel Pin ◽

Length Changes

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Neutronic analysis of fuel pin design for the long-life core in a pressurized water reactor

Nuclear Science and Technology ◽

10.53747/jnst.v11i1.127 ◽

2021 ◽

Vol 11 (1) ◽

pp. 9-15

Author(s):

Van Khanh Hoang ◽

Vinh Thanh Tran ◽

Dinh Hung Cao ◽

Viet Ha Pham Nhu

Keyword(s):

Coolant Temperature ◽

Pressurized Water Reactor ◽

Fuel Temperature ◽

Pressurized Water ◽

Water Reactor ◽

Fuel Model ◽

Reactivity Coefficients ◽

Fuel Pin ◽

Safety Parameters ◽

Long Life

This work presents the neutronic analysis of fuel design for a long-life core in a pressurized water reactor (PWR). In order to achieve a high burnup, a high enrichment U-235 is traditionally considered without special constraints against proliferation. To counter the excess reactivity, Erbium was selected as a burnable poison due to its good depletion performance. Calculations based on a standard fuel model were carried out for the PWR type core using SRAC code system. A parametric study was performed to quantify the neutronically achievable burnup at a number of enrichment levels and for a numerous geometries covering a wide design space of lattice pitch. The fuel temperature and coolant temperature reactivity coefficients as well as the small and large void reactivity coefficients are also investigated. It was found that it is possible to achieve sufficient criticality up to 100 GWd/tHM burnup without compromising the safety parameters.

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Perhitungan Perubahan Reaktivitas Pada Reaktor Serba Guna G.A. Siwabessy Akibat Pengoperasian Power Ramp Test Facility

Prosiding SNFA (Seminar Nasional Fisika dan Aplikasinya) ◽

10.20961/prosidingsnfa.v4i0.35919 ◽

2019 ◽

Vol 4 ◽

pp. 121

Author(s):

A Suparmi ◽

Tuti Dwi Setyaningsih ◽

Suharyana Suharyana ◽

Fuad Anwar ◽

Riyatun Riyatun

Keyword(s):

Reactor Core ◽

Test Facility ◽

Pressurized Water Reactor ◽

Pressurized Water ◽

Water Reactor ◽

Ramp Test ◽

Fuel Pin ◽

Safe Limit ◽

Reactor Operating ◽

Test Fuel

Abstract: Power Ramp Test Facility (PRTF) is one of the irradiation facility contained in the Multipurpose Reactor GA Siwabessy. This facility is used to test the reactor fuel element pin-type Pressurized Water Reactor. As a result of the entry of foreign bodies cause changes reactor conditions, one of which is expressed with the amount of reactivity to assess the safety of the reactor due to the operation PRTF. PRTF operation simulation and calculation is done using software neutronics MCNP6. Test UO2 fuel enriched assumed at 5% with constant power reactor operating at 15 MW and test fuel pin placed on PRTF within 0, 20, 40, 60, 80, 100, 120, and 140 mm from the centre of the reactor core. Change of reactivity values required in order to secure the reactor, maximal value is 0,5%. The calculation were obtained at each position is (; ; ; ;; ; ; ). Change of reactivity values smaller than the safe limit. Therefore, the study of reactivity changes PRTF operation to test fuel pin is secure.Abstrak: Power Ramp Test Facility (PRTF) merupakan salah satu fasilitas iradiasi yang terdapat pada Reaktor Serba Guna G.A. Siwabessy. Fasilitas ini digunakan untuk menguji pin elemen bahan bakar reaktor tipe Pressurized Water Reactor. Akibat dari masuknya benda asing menyebabkan perubahan kondisi reaktor, salah satunya dinyatakan dengan besaran reaktivitas untuk mengkaji keselamatan reaktor akibat pengoperasian PRTF. Simulasi pengoperasian PRTF dan perhitungan netronik dilakukan menggunakan perangkat lunak MCNP6. Bahan bakar uji UO2 diasumsikan diperkaya sebesar 5% dengan daya operasi reaktor konstan sebesar 15 MW. Pin bahan bakar uji diletakkan pada PRTF berjarak 0, 20, 40, 60, 80, 100, 120, dan 140 mm dari arah pusat teras reaktor. Nilai perubahan reaktivitas yang dipersyaratkan agar reaktor aman adalah , sedangkan nilai perubahan reaktivitas dari penelitian pada masing-masing posisi dari pusat reactor adalah (; ; ; ;; ; ; ) . Nilai perubahan reaktivitas akibat masuknya pin bahan bakar di PRTF mempunyai nilai perubahan reaktivitas 1/10 kali lebih kecil daripada batas aman. Oleh karena itu, ditinjau dari kajian nilai perubahan reaktivitas maka pengoperasian PRTF untuk uji pin bahan bakar adalah aman.

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