Although recurrent malignancy is the most frequent indication for second stem cell transplantation (2nd SCT), there are few reports that include sufficiently large numbers of patients to enable prognostic factor analysis. This retrospective study includes 150 patients who underwent a 2nd SCT for relapsed acute myeloblastic leukaemia (n = 61), acute lymphoblastic leukaemia (n = 47) or chronic myeloid leukaemia (n = 42) after a first allogeneic transplant (including 26 T‐cell‐depleted). The median interval between the first transplant and relapse, and between relapse and second transplant was 17 months and 5 months respectively. After the 2nd SCT, engraftment occurred in 93% of cases, 32% of patients developed acute graft‐vs.‐host disease (GVHD)  grade II and 38% chronic GVHD. The 5‐year overall and disease‐free survival were 32 ± 8% and 30 ± 8%, respectively, with a risk of relapse of 44 ± 12% and a transplant‐related mortality of 45 ± 9%. In a multivariate analysis, five factors were associated with a better outcome after 2nd SCT: age < 16 years at second transplant; relapse occurring more than 12 months after the first transplant; transplantation from a female donor; absence of acute GVHD; and the occurrence of chronic GVHD. The best candidates for a second transplant are likely to be patients with acute leukaemia in remission before transplant, in whom the HLA‐identical donor was female and who relapsed more than 1 year after the first transplant.

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Summary The comprehension of severe criticality accident is a key issue in Gen‐IV neutronics and safety. Within the future zero‐power experimental physics reactor (ZEPHYR), to be built in Cadarache in the next decade, innovative approaches to reproduce high temperature partially degraded Gen‐IV cores into a critical facility is being investigated. This work presents the first attempt to represent a fuel assembly of sodium‐cooled fast reactor severe criticality accident based on surrogate models. One identified way to construct such representative configuration is to use MASURCA plates stockpile (MOX, UOx, Na, U, and Pu metal) in a fast/thermal coupled core to model a stratified molten assembly. The present study is the first step in a more global approach to full core analysis. The approach is based on a nature‐inspired metaheuristic algorithm, the particle swarm optimization algorithm, to find relevant ZEPHYR configuration at 20°C that exhibits characteristics of (2000‐3000°C) molten MOX assembly in a stratified metal arrangement in a reference sodium‐cooled fast reactor core. Thus, the underlying research question of this study is whether it is possible to represent temperature‐related reactivity effects occurring at fuel meltdown temperatures in a power reactor as density‐related reactivity effects at the operation temperature of a zero‐power reactor, and if so, how should it be done? The calculations are based on a Serpent‐2 Monte Carlo sensitivity and representativity analysis using the Cadarache's cross sections covariance data (COMAC). The single fuel assembly studies show that it is possible to represent the multiplication factor with a representativity factor greater than 0.98. As for reactivity variations, it is possible to achieve a satisfactory representativity factor of above 0.85 in all the presented cases. The representativity process demonstrates that temperature effects could be translated into density effects with good confidence. A complementary analysis on modified nuclear data covariance matrix demonstrates the importance of selecting consistent and robust uncertainties in the particle swarm optimization algorithm. This work provides insights on the behavior of the representativity scheme in different core states and shades some light on the problem in hand.

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MINERVE is a two-zone pool type zero power reactor operated by CEA (Cadarache, France). Kinetic parameters of the core (prompt neutron decay constant, delayed neutron fraction, generation time) have been recently measured using various pile noise experimental techniques, namely Feynman-, Rossi-and Cohn-. Results are discussed and compared to each other's.The measurement campaign has been conducted in the framework of a tri-partite collaboration between CEA, SCK•CEN and PSI. Results presented in this paper were obtained thanks to a time-stamping acquisition system developed by CEA. PSI performed simultaneous measurements which are presented in a companion paper.Signals come from two high efficiency fission chambers located in the graphite reflector next to the core driver zone. Experiments were conducted at critical state with a reactor power of 0.2 W. The core integral fission rate is obtained from a calibrated miniature fission chamber located at the center of the core. Other results obtained in two sub-critical configurations will be presented elsewhere.Best estimate delayed neutron fraction comes from the Cohnmethod: 747 ± 15 pcm (1 ). In this case, the prompt decay constant is 79 ± 0.5 s -1 and the generation time is 94.5 ± 0.7 μs. Other methods give consistent results within the confidence intervals.Experimental results are compared to calculated values obtained from a full 3D core modeling with the CEA-developed Monte Carlo code TRIPOLI4.9 associated with its continuous energy JEFF3.1.1-based library. A very good agreement is observed for the calculated delayed neutron fraction (748.7 ± 0.4 pcm at 1 ), that is a difference of -0.3% with the experiment. On the contrary, a 10% discrepancy is observed for the calculated generation time (104.4 ± 0.1 μs at 1 ).

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