Call Number (LC) Title Results
Tk9203.P7 O75 1988 Sizewell B : an anatomy of the inquiry / 1
TK9203.P7 P74 2022 Pressurized Heavy Water Reactors : CANDU /
Pressurized Heavy Water Reactors : Atucha II / 		2
TK9203.P7 T6 1996 Thermal analysis of pressurized water reactors 1
TK9203.P8 Fast pulsed and burst reactors a comprehensive account of the physics of both single burst and repetitively pulsed reactors / 1
TK9203.P8 S36 2017 U. S. fast burst reactors : design and operational history / 1
TK9203.S6 Superphenix : technical and scientific achievements / 1
TK9203.S6 B46 2013 Benchmark analyses on the natural circulation test performed during the Phenix end-of-life experiments : final report of a coordinated research project 2008-2011. 2
TK9203.S6 R35 2015eb Sodium fast reactors with closed fuel cycle / 3
TK9203.W37 Thermal-hydraulics of water cooled nuclear reactors
Materials and water chemistry for supercritical water-cooled reactors /
Handbook on thermal hydraulics in water-cooled nuclear reactors. 		6
TK9203.W37 A23 2005 Accident analysis for nuclear power plants with graphite moderated boiling water RBMK reactors. 1
TK9203.W37 A38 1989 Advanced water-cooled reactor technologies : rationale, state of progress and outlook / 1
TK9203.W37 A43 American national standard single failure criteria for light water reactor safety-related fluid systems / 1
TK9203.W37 A44 1993 American national standard for solid radioactive waste processing system for light-water-cooled reactor plants / 1
TK9203.W37 .C688 2018eb Current State of Research on Pressurized Water Reactor Safety
Current State of Research on Pressurized Water Reactor Safety. 		2
TK9203.W37 D47 2016eb Design safety considerations for water cooled small modular reactors incorporating lessons learned from the Fukushima Daiichi accident. 2
TK9203.W37 E345 2012 Efficient Water Management in Water Cooled Reactors 1
TK9203.W37 G66 2011 Good practices for water quality management in research reactors and spent fuel storage facilities.
Good practices for water quality management in research reactors and spent fuel storage facilities 		2
TK9203.W37 H43 2014 Heat transfer behaviour and thermohydraulics code testing for supercritical water cooled reactors (SCWRs) 1
TK9203.W37 M474 2023 Methodologies for assessing pipe failure rates in advanced water cooled reactors. 1
TK9203.W37 N38 2012 Natural circulation phenomena and modelling for advanced water cooled reactors
Natural circulation phenomena and modelling for advanced water cooled reactors. 		2