Final report of shielding calculations performed at ECN Petten for ITER CTA task D4/EU
Description
In this report the final results are presented of neutronics calculations performed at ECN Petten in the framework of ITER task D4. It is shown, that self-shielding in the unresolved resonance region, which is not taken into account in MCNP, will increase the fast neutron flux in ITER shielding blanket calculations with at least 10%. A method is presented, with which an approximate calculation of the effect is possible. It is observed, that homogenisation of stainless steel and water in neutronics calculations is not allowed for accurate calculations. Calculations were performed with several sources of cross section data (EFF-1, EFF-2.4 and FENDL-1.0). It is shown, that systematic differences occur between the results from different calculations. However, a fair agreement is observed if results of EFF-2.4 and FENDL-1.0 calculations are compared. Sensitivity and uncertainty studies show, that the uncertainty in the energy integrated flux in a relevant energy range amounts to 15%. This uncertainty is mainly due to uncertainties in the total cross section and the elastic angular distribution of Fe. (orig.)
Availability note (English)
MF available from INIS under the Report Number; Also available from the author at the Netherlands Energy Research Foundation (ECN), Petten (NL).Files
28011350.pdf
Files
(634.1 kB)
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Additional details
Publishing Information
- Imprint Pagination
- 37 p.
- Report number
- ECN-C--95-045
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 28011350
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BENCHMARKS; BREEDING BLANKETS; FLUX DENSITY; ITER TOKAMAK; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; ONE-DIMENSIONAL CALCULATIONS; SELF-SHIELDING; STAINLESS STEELS; TOTAL CROSS SECTIONS; TWO-DIMENSIONAL CALCULATIONS; WATER
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; CROSS SECTIONS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; OXYGEN COMPOUNDS; RADIATION FLUX; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS; TRANSPORT THEORY
Optional Information
- Contract/Grant/Project number
- Contract ERB5000 CT 940038; Contract EC NET (NET/93-350); Project Number ECN 1.1676