Post-test analysis of P5 experiment in PANDA facility with TRAC-BF1 code

Corfu Marco Polo Pocket Guide

Marco Polo Travel

Crete Marco Polo Pocket Guide

Marco Polo Travel

Santorini Marco Polo Pocket Guide

Marco Polo Travel

Gender and the Spatiality of Blackness in Contemporary AfroFrench Narratives

Polo B. Moji

Travels of Marco Polo

Marco Polo

Cyprus Marco Polo Pocket Guide

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Malta Marco Polo Pocket Guide

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California Marco Polo Spiral Guide

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London Marco Polo Spiral Travel Guide

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Cast Iron Skillet Cookbook Mediterranean Style

Polò Useful Publishing

Portugal Marco Polo Spiral Guide

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Released

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Madeira Marco Polo Spiral Guide

Marco Polo Travel Publishing

Quaestorship in the Roman Republic

Francisco Pina Polo

Retrieved

Amber Polo

Pharaoh and the Librarian

Amber Polo

Neuronal Factors

Jose Regino Perez-Polo

Water Polo Notebook

Water Polo Enthusiast

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Amber Polo

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Mallorca Marco Polo Spiral Guide

Marco Polo Travel

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Sixto Polo Fontanez

Morocco Marco Polo Pocket Guide

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True and the Rainbow Kingdom Coloring Book

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Amber Polo

Marrakesh Marco Polo Spiral Guide

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Heads in the Clouds

Amber Polo

Beanie Boo's Coloring Book

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Antonio JIMÉNEZ POLO

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Dark Psychology

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Scotland Marco Polo Map

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Water Polo Journal - Water Polo Is in My DNA

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Adventures of Marco Polo, the Great Traveler

Marco Polo

Socialism

Rafael Polo

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Elephant Polo Publishing

Consequence study of a beyond-design-basis earthquake affecting the spent fuel pool for a U.S. Mark I boiling water reactor

Andrew Barto

Qing zheng, shui zhu

Anqi Cheng

BWR puranto tōkeiteki anzen hyōka shuhō no seibi

Genshiryoku Anzen Kiban Kikō

Zheng zhu

Xianzhu Jiang

Sanjigen kaku netsudō tokusei kaiseki kōdo e no RIA-ji kato futtō moderu no kumikomi.

Roshin sonshō ni taisuru risuku jūyōdo ni motozuku haikan no kensa bui, hōhō tō ni kansuru kentō (BWR).

Akushidento manejimentso chishiki bēsu seibi ni kansuru hōkokusho

Explosive boiling of superheated cryogenic liquids

V. G. Baĭdakov

Experimental and Analytical Modeling of Natural Circulation and Forced Circuluation BWRS

Masahiro Furuya

The 2007 Import and Export Market for Electric Ovens, Cookers, Cooking Plates, Boiling Rings, Grillers, and Roasters in United States

Philip M. Parker

The World Market for Electric Ovens, Cookers, Cooking Plates, Boiling Rings, Grillers, and Roasters

Philip M. Parker

Accident Analysis for Nuclear Power Plants With Graphite Moderated Boiling Water Rbmk Reactors

Kiki furajiriti hyōka (BWR puranto).

Futtōsuigata genshiro no kaku netsusuiryoku anteisei kaiseki shuhō no seibi ni kansuru hōkokusho

Genshiryoku Anzen Kiban Kikō

Standard technical specifications

Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, Version 3690, code

F. Odar

Reflections of a community-- Boiling Springs remembered

Boiling Springs Friends Of The Library

PWR and BWR pressure vessel fluence calculation benchmark problems and solutions

LAPUR5.2 verification and user's manual

A. Escrivá

LAPUR5.2 verification and user's manual

A. Escriva

Assessment of single recirculation pump trip transient in Santa Maria de Garona Nuclear Power Plant with TRAC-BF1/MOD1, version 0.4

C García de la Rúa

Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, Version 3690, code

F Odar

Irradiation-assisted stress corrosion cracking of model austenitic stainless steel alloys

Evaluation of risk associated with intergranular stress corrosion cracking in boiling water reactor internals

Nowadays tools for graphical post-processing of TRAC-BF1 results

P. Corcuera

Confrentes NPP (BWR/6) ATWS (MSIVC) analysis with TRAC-BF1

Drywell debris transport study

Risk comparisons of scheduling preventive maintenance for boiling water reactors during shutdown and power operations

Single-phase and two-phase natural circulation tests in the PUMA facility

RAMONA-4B, a computer code with three-dimensional neutron kinetics for BWR and SBWR system transients

Enhancement of R123 pool boiling by the addition of hydrocarbons

Mark A. Kedzierski

Round robin pretest analyses of a steel containment vessel model and contact structure assembly subject to static internal pressurization

Vincent K. Luk

RAMONA-4B, a computer code with three-dimensional neutron kinetics for BWR and SBWR system transients

Piping benchmark problems for the Westinghouse AP600 standardized plant

Simplified model of decontamination by BWR steam suppression pools

D. A. Powers

Final safety evaluation report related to the certification of the advanced boiling water reactor design

Final results of the XR2-1 BWR metallic melt relocation experiment

Randall Owen Gauntt

Scientific design of Purdue University multi-dimensional integral test assembly (PUMA) for GE SBWR

Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions

Revised analyses of decommissioning for the reference boiling water reactor power station

Estimating boiling water reactor decommissioning costs

M. C. Bierschbach

Status report

Applications of reliability degradation analysis

W. E. Vesley

Workshop on Gate Valve Pressure Locking and Thermal Binding, held at Marriott Hotel, New Orleans, LA, February 4, 1994

Workshop on Gate Valve Pressure Locking and Thermal Binding (1994 :).).

Parametric study of the potential for BWR ECCS strainer blockage due to LOCA generated debris

Aging study of boiling water reactor high pressure injection systems

D. A. Conley

Standard technical specifications

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.

Analysis of long-term station blackout without automatic depressurization at Peach Bottom using MELCOR (version 1.8)

I. K. Madni

Final safety evaluation report related to the certification of the advanced boiling water reactor design

Risk impact of BWR technical specifications requirements during shutdown

B. D. Staple

Parametric study of the potential for BWR ECCS strainer blockage due to LOCA generated debris

Effects of aging on BWR core isolation cooling systems

B. S. Lee

High pressure coolant injection (HPCI) system risk-based inspection guide for Browns Ferry Nuclear Power Station

S. Wong

Management of ATWS by boron injection

M. P. Dias

TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor

R. P. Martin

Assessment of RELAP5/MOD2 against ECN-reflood experiments

A. Woudstra

Assessment of the turbine trip transient in Cofrentes NPP with TRAC-BF1

F. Castrillo

High pressure coolant injection (HPCI) system risk-based inspection guide for Enrico Fermi atomic power plant, unit 2

M. Villaran

High pressure coolant injection (HPCI) system risk-based inspection guide for Dresden Nuclear Power Station, units 2 and 3

W. Shier

XSOR codes users manual

Hong-Nian J. Jow