Neutron lifetime measurements and analysis in a heterogeneous thermal reactor system

Ball, R.M.; Hoovler, G.S.; Parma, Edward J.; Selcow, E.C.; Cerbone, R.J.

doi:10.1063/1.43152

Cited by 1 publication

(2 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The reactor operates at ambient conditions anti produces less than tO watts of totat power. A complete description of the reactor core is found in (Parma et al 1993). The explicit model developed to represent the reactor system is presented in Figure 1, and contains the inner and outer aluminum canisters, fuel regions, water radial reflector, polyethylene axial reflectors, t6"p and bottom grid plates, and the outer aluminum tank which has a radius of 36 cre.…”

Section: Initial Criticality and Excess Reactivitymentioning

confidence: 99%

See 1 more Smart Citation

MCNP benchmark analyses of critical experiments for the Space Nuclear Thermal Propulsion program

Selcow

Cerbone

Ludewig

et al. 1993

AIP Conference Proceedings

Self Cite

View full text Add to dashboard Cite

Benchmark analyses have been performed of Particle Bed Reactor (PBR) critical experiments (CX) using the MCNP radiation transport code. The experiments have been conducted at the Sandia National Laboratory re.actor facility in support of the Space Nuclear Thermal Propulsion (SNTP) program. The test reactor is a nineteen element water moderated and reflected thermal system. 'A series of integral experiments have been carried out to test the capabilities of the radiation transport codes to predict the performance of PBR systems. MCNP was selected as the preferred radiation analysis tool lhr the benchmark experiments. Comparison between experimental and calculational results indicate very good agreement. This paper describes the analyses of benchmark experiments designed to quantify the accuracy of the MCNP radiation transport code for predicting the pertbrmance characteristics ot PBR reactors.

show abstract

Section: Initial Criticality and Excess Reactivitymentioning

confidence: 99%

“…Several other companion papers presented in this symposium will discuss the overall description ot" the desien and safety aspects of the reactor (Parma et ai. 1993) and the experimental dcsi:gn, _,ctup, operations, results, and measurement errors (Ball et al 1993 andHoovler et ai. 1993).…”

Section: Introdiictionmentioning

confidence: 99%