Calculation code for nuclear cross section

Code package:

• The code [ncs.doc], written in Delphi (download, rename to “ncs.zip”, then extract)

Calculation code for spherical nuclear reactor

The governing equation being used is the steady state neutron diffusion equation:

Numerical schemes being used are:

• Central finite difference for flux calculation
• Gauss-Siedel and S.O.R for flux calculation
• Power method for criticality calculation

Code package:

• Manual (English)
• Code [snr.doc], written in Delphi (download, rename to “snr.zip”, then extract)

Flowchart of the code:

Some previews:

 

The IRIS Reactor Technical Specifications

Disclaimer:
Information presented in this article are based on publicly available data of the IRIS reactor project, as properly cited from the original source. This article is NOT part of the official IRIS project led by Westinghouse. For more reliable information, the reader should refer to any official websites and information sources of the IRIS project and/or the IRIS consortium. All trademarks and registered trademarks shown in this article are the property of their respective owners.

General Plant Data
Core thermal power	1000 MWt [ref.2-page35]
Power Plant Net Output	335 MWe [ref.2-page35]
Nuclear Steam Supply System
Number of coolant loops	Integral RCS [ref.2-page35]
Steam temperature/pressure	317/5.8 °C/MPa [ref.2-page35]
Feedwater temperature/pressure	224/6.4 °C/MPa [ref.2-page35]
Reactor Coolant System
Total core flow rate	36000 kg/s [ref.3-page53]
Primary coolant flow rate	4700 kg/s [ref.2-page35]
Reactor operating pressure	15.5 MPa [ref.2-page35]
Core inlet temperature	292 °C [ref.2-page35]
Core (riser) outlet temperature	330 °C [ref.2-page35]
Reactor Core
Fuel assembly total length	5.207 m [ref.2-page35]
Fuel inventory	48.5 tU [ref.2-page35]
Average linear heat rate	10.0 kW/m [ref.2-page35]
Average core power density (volumetric)	51.26 kW/l [ref.2-page35]
Specific power (= core thermal power/fuel inventory)	20.6186 kW/kg-HM
Fuel material	Sintered UO2 [ref.2-page35] Westinghouse standard PWR fuel
Fuel average density	96% Theoretical Density [ref.3-page203] UO2-TD = 10.96 g/cc
Rod array	Square 17×17 XL [ref.2-page38,ref.5-page155]
Number of fuel assemblies	89 [ref.2-page35]
Number of fuel rods/assembly	264 [ref.2-page35]
Fuel pellet diameter	8.19 mm [ref.1-page634]
Pellet-clad gap	0.082 mm [ref.1-page634]
Clad thickness	0.572 mm [ref.1-page634]
Outer diameter of fuel rods	9.5 mm [ref.2-page35,ref.5-page155]
Pitch (center-to-center)	12.54 mm [ref.1-page634]
P/D	1.32 [ref.3-page34]
Average H/HM ratio (Hydrogen to Heavy Metal ratio)	3.4 [ref.3-page34]
Volume fractions	33.50% fuel 54.92% moderator 11.58% structure
Volume ratios	fuel-to-moderator: 0.6099 moderator-to-fuel: 1.6396
Enrichment	4.95 Wt % U-235 [ref.2-page35]
Coolant average density	0.7295 g/cc [ref.6-page31] 0.727664 g/cc (calculated from enrichment and H/HM data)
Equilibrium cycle length	30-48 months [ref.2-page35]
Average discharge burnup	60 000 MWd/tU [ref.2-page35]
Reactor Pressure Vessel
Cylindrical shell inner diameter	6.21 m [ref.2-page35]
Wall thickness of cylindrical shell	28.5 cm [ref.2-page35]
Total height (including clossure head)	22.2 m [ref.5-page154]
Active core height (core barrel)	426.7 cm [ref.5-page156]
Active core inner diameter (core barrel)	241.27 cm [ref7-page45] calculated from core thermal power, power density, and active core height
Active core outer diameter (core barrel)	285 cm [ref.5-page157]
Steam Generators
Type	Vertical, helical coil tube bundle, once-through, superheated [ref.2-page35]
Number	8 [ref.2-page35]
Thermal capacity (each SG)	125 MWt [ref.2-page35]
Number of heat exchanger tubes (each SG)	656 [ref.2-page35]
Reactor Coolant Pump
Type	Spool type, fully immersed [ref.2-page35]
Number	8 [ref.2-page35]
Pump head	19.8 m [ref.2-page35]
Primary Containment
Type	Pressure suppression, steel [ref.2-page35]
Geometry	Spherical, 25 m diameter [ref.2-page35]
Design pressure/temperature	1300/200 kPa/°C [ref.2-page35]

References

1. Duderstadt, James J. and Louis J. Hamilton. (1976), Nuclear Reactor Analysis, John Wiley & Sons, Inc, New York.
2. IRIS@NuclearNews
3. MIT Master Thesis – Thermal Hydraulic Performance Analysis of a Small Integral PWR Core
4. J-NucEngDes – Carelli – The exciting journey of designing an advanced reactor
5. J-NucEngDes – Carelli et al. – The design and safety features of the IRIS reactor
6. Data from US NRC
7. Reactor dosimetry in the 21st century

Useful links

• IRIS official website
• IRIS – 2003 FINAL TECHNICAL PROGRESS REPORT
• IRIS@wikipedia
• Water density as a function of temperature and pressure
• IRIS dimension from google books

Standard PWR nuclear fuel assembly (17×17) technical specifications

Geometry	Square 17×17 matrix
Fuel assembly dimension	Square 214 x 214 mm
Composition per assembly	Total: 289 Fuel: 264 Control rod guide thimble: 24 Instrumentation thimble: 1
Fuel material	UO2 (U235,U238,Oxygen)
Cladding material	Zircaloy-4 98.23 weight % zirconium with 1.45% tin, 0.21% iron, 0.1% chromium, and 0.01% hafnium
Gap filler	Helium gas
Fuel average density	95 – 96% Theoretical Density UO2-TD = 10.96 g/cc
Moderator (coolant)	light water (H2O) average density 0.7295 gr/cc
H/HM ratio (hydrogen to heavy metal ratio)	1.7 – 3.4 (depends on enrichment level)
Enrichment	2.5 – 5 Wt % U235
Fuel pellet diameter	8.19 mm
Pellet-clad gap	0.082 mm
Clad thickness	0.572 mm
Outer diameter of fuel rods	9.5 mm
Pitch (center-to-center)	12.54 mm
P/D	1.32

Related Links

• Data from Oak Ridge National Laboratory
• Data from KAERI Nuclear Training Center
• Data from dspace@MIT
• Data from US NRC
• Zircalloy@wikipedia
• Water density as a function of temperature and pressure

Free Download: Nuclear Reactor Analysis Code

• Download this file >> xprenpac.doc
• Change the filename to “xprenpac.zip”
• Extract it
• Read the  manual: [pdf | quickview]
• First, execute the “Project1.exe” to test-run it
• And then you can execute the “Project1.dpr” to view the entire source code (Borland Delphi 7 is required)
• Enjoy it!

BATAN tidak boleh ragu bicara tentang PLTN

Dr. Hudi Hastowo

Pada hari Kamis, 11 September 2008, saya menghadiri seminar tentang nuklir yang disampaikan oleh pak kepala BATAN, Dr. Hudi Hastowo. Seminar ini diadakan di Campus Center ITB, dari jam 9 sampai 10 pagi, dengan moderator pak Rektor ITB, Prof. Dr. Djoko Santoso. Pada seminar ini pak kepala BATAN menjelaskan tentang aplikasi nuklir pada berbagai bidang, seperti kesehatan & pengobatan, pangan & pertanian, dan tentu saja PLTN. Yang membuat saya heran, dari 60 menit waktu yang disediakan, pak kepala batan menggunakan sekitar 55 menit untuk memaparkan pemanfaatan nuklir di bidang2 non energi (alias non PLTN), dan hanya menggunakan sekitar 5 menit terakhir saja untuk berbicara mengenai PLTN! ada apa ini? mengapa BATAN tampak ragu (takut?) bicara mengenai PLTN? padahal kita semua tahu bahwa untuk bidang2 non PLTN, seperti pertanian, pengobatan, dsb, tidak ada seorang-pun yang keberatan, hal2 seperti ini buat apa disosialisasikan lagi?

Justru yang mendapat banyak tantangan adalah tentang PLTN, adakah diantara kita yang pernah mendengar Greenpeace berdemo menentang pengobatan kanker dengan menggunakan nuklir? atau demo menolak penggunaan radiasi nuklir untuk merekayasa bibit pertanian varietas unggul? TIDAK! mereka berdemo (baca : menghasut massa) untuk menolak PLTN, tapi mereka tidak pernah berdemo menolak aplikasi nuklir non PLTN bukan? dengan demikian menurut saya yang harus menjadi fokus sosialisasi dan kampanye nuklir adalah tentang PLTN, sedangkan aplikasi nuklir non PLTN hanya sebagai tambahan saja, bukan malah sebaliknya! spesifik mengenai seminar nuklir kemarin di CC-ITB, pak kepala BATAN tidak perlu khawatir bahwa audiens tidak akan mengerti bila anda menjelaskan tentang, misalnya safety system PLTN, audiens anda kemarin itu terdiri dari para mahasiswa S1, S2, S3, dan juga dosen, jadi Insya Allah mereka akan cukup mengerti bila anda menjelaskan sedikit teknis tentang PLTN.

Menurut saya, yang akan membawa perubahan besar bagi bangsa kita adalah aplikasi nuklir pada PLTN, PLTN-lah yang akan mengawal perjalanan pembangunan bangsa kita menuju era industri yang sebenarnya, misalnya melalui penyediaan supply listrik murah dan stabil, yang akan mendukung industri manufaktur dan perdagangan internasional di negara kita. Hal2 seperti inilah yang menurut saya harus disampaikan secara intensif kepada masyarakat, yaitu mengenai outline analisis keselamatan PLTN, dan alasan2 logis tentang mengapa kita harus ber-PLTN bila tidak ingin tertinggal dari negara2 lain. Kesimpulannya, kalau BATAN saja, yang jelas2 memang expert nuklir, ragu bicara tentang PLTN, bagaimana orang lain bisa tidak ragu?