Pd

P.F.A. de Leege

52 records found

Member NEA JEFF working group on Benchmark testing, date processing and eveluation, NJOY user's group

Member NEA JEFF working group on Benchmark testing, date processing and evaluation, NJOY user's group

Neutron activation of holmium poly)L-lactic acid) microspheres for hepatic arterial radioembolization: a validation study

Member NEA JEFF working group on Benchmark testing, date processing and evaluation, NJOY user's group

Member NEA JEFF working group on Benchmark testing, date processing and evaluation, NJOY user's group

Multigroup coupled neutron-gamma cross-section library for deterministic and Monte Carlo borehole-logging analysis

HOR HEU/LEU core conversion: 8 years of experience

Conceptual design of a novel high frame rate fast-neutron radiography facility

Review van de HABOG Criticaliteits Analyse, PNR-131-2005-006, September 2005, vertrouwelijk. In opdracht van COVRA NV
Report (2005) - P.F.A. de Leege (author)

Reactor physics aspects of low void fuel-phase 2, Final report, Contract No: 87055-04-0269, Rapport PNR-131-2005-001, March 2005

Monte Carlo calculation of the effects of delayed neutron precursor transport in molten salt reactors

Optimisation of fast-neutron radiography by use of a new imaging quality concept called Figure of Merit

HOR, criticality comparison using a nodal code, Monte Carlo codes and plant data

Generation and performance of a multigroup coupled neutron-gamma cross-section library for deterministic and Monte Carlo borehole logging analysis

Progress report: Contract No.: 87055-04-0269 Title: Reactor physics aspects of low void fuel - phase 2. Rapport IRI-131-2004-005.
Report (2004) - P.F.A. de Leege (author)

MCNP based calculation of reactivity loss in circulating fuel reactors

Co-chair session T2-1 Seventh International Conference on Nuclear Safety (ICNC2003), Tokai, Ibaraki, Japan, 20-24 October 2003

Criticality safety using Monte-Carlo and nodal methodes for a small beryllium reflected core

Upgrading the HOR: an upgrading study for the HOR

MCNP based calculation of reactivity loss due to fuel circulation in molten salt reactors