M . B . E m m e t t Oak R i d g e N a t i o n a l L a b o r a t o r y Oak R i d g e , T e n n e s s e eliability or responsibility for the accuracy, completeness ur usefulriess of any information. apparatus. product or process disclosed. or represent! that its use would not infringe priwtely owned rights. The MORS"cl'4 Code System t a s been i n c o n t i n u o u s u s e f o r s e v e r a l y e a r s now and h a s s u b s e q u e n t l y undergone much r e v i s i o n . I n a d d i t i o n t o t h i s , i t s development h a s continued; and it:; a p p l i c a t i o n s have expanded i n t o new areas r e q u i r i p g development of a d d i t i o n a l computer programs. Because t h e documentation of t h e v d r i c u s a o d u l e s o f MORSE i s s c a t t e r e d through several r e p o r t s and because o f . t h e numerous r e v i s i o n s r e q u i r e d t o g e t t h i s documentation up-to-dara f o r t h e c u r r e n t v e r s i o n s of r o u t i n e s , i t was decided t o w r i c e one c l m p i e t e r e p o r t d e s c r i b i n g a l l a s p e c t s o f t h e PURSE system and r e l a t e d conguter codes. As might b e e x p e c t e d , t h i s r e p o r t draws h e a v i l y from t h e p r e v i o u s r e p o r t s . A l l i n f o r m a t i o n n e c e s s a r y t o u s e t h e s e ccdes is c o n s o l i d a t e d i n t o one r e p o r t . There ;r2 s e c t i o n s L o n t a i n i n g d e s c r i p t i o n s of t h e MORSE and PICTURE5 codes, i n p u t d e s c r i p t i o n s , sample problems, d e r i v a t i o n s of t h e p h y s i c a l e q u a t i o n s and e x p l a n a t i o n s o f t h e v a r i o u s e r r o r messages. This r e p o r t a t t e m p t s t o docu.;ler?t the IBX-360, UNIVAC-1108 and CDC-6600 v e r s i o n s of MOXSE tlird i t s a u x i l i a r ycodes. Most o p t i o n s are a v a i l a b l e on a l l thr'i.2 machines, b u t some are n o t becausc one or more of t h e machines does n o t have some p a r t i c u l a r c a p a h i l i t v . I t i s expected t h a t some of t h e p a r t s b e i n g p u b l i s h e d now w i l l b e expanded, i n p a r t i c u l a r , t h e semple problem rlotebook i n P a r t 3 on t h e UNTVAC machine w i l l a l s o be added. Because t i m e was a t a premium, no a t t e m p t was made t o update flow c h a r t s and i n c l u d e them. Users may refer t o t h e p r e v i o u s r e p o r t s ( s e e r e f s . 1-4 on page 1 . 2 -l ) , b u t s h o u l d keep i n mind t h a t some of t h e c h a r t s are o u t of d a t e . c3 1.1-2This r e p o r t w i l l d e s c r i b e o n l y t h e MORSE w i t h c o m b i n a t o r i a l. " / geometry (CG) and n o t t h e OSR-type g e o m e t r i e s which are no l o n g e r m a i n t a i n e d i n MORSE. This d e c i s i o n was made b e c a u s e CG w i l l h a n d l e a l l t y p e s of g e o m e t r i e s e x p e d i t i o u s l y and because i t i s q u i t e cumbersome t o m a i n t a i n m u l t i p l e v e r s i o n s o f a code as l a r g e and c o m p l i c a t e d as MORSE.It is worth n o t i...

The Fissile Materials Disposition Program (FMDP) sponsored the development and solution of a benchmark set to allow comparison of criticality, shielding, and decay heat computations for disposition of plutonium materials in a VVER-1000 assembly. This paper documents the United States contribution to that study.

T h l s Work Sponsored by The Defense Nuclear Agency and DOE O f f l c e o f Energy Technology, D l v l s l o n o f Reactor Research 8 Technology *Computer Sciences D i v i s l o n OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION f o r t h e DEPARTMENT OF ENERGY

Whenever a decision is made to newly install the SCALE nuclear criticality safely software on a computer system, the user should run a set of verification and validation (V&V) test cases to demonstrate that the software is properly installed and functioning correctly. This report is intended to serve as a guide for this V&V in that it specifies test cases to run and gives expected results. The report describes the V&V that has been performed for the nuclear criticality safety software in a version of SCALE-4. 1 The verification problems specified by the code developers have been run, and the results compare favorably with those in the SCALE 4.2 baseline. 2 The results reported in this document are from the SCALE 4.2P version which was run on an IBM RS/6000 workstation. These results verify that the SCALE-4 nuclear criticality safely software has been correctly installed and is functioning properly. A validation has been performed for KENO V.a 3 utilizing the CSAS25 (ref. 4) criticality sequence and the SCALE 27-group cross-section library for ^U, 235 U, and 239 Pu fissile systems in a broad range of geometries and fissile fuel forms. The experimental models used for the validation were taken from three previous validations of KENO V.a. A statistical analysis of the calculated results was used to determine the average calculational bias and a subcriticai k,. ff criteria for each class of systems validated. Included in the statistical analysis is a means of estimating the margin of subcriticality in k^. This validation demonstrates that KENO V.a and the 27-group library may be used for nuclear criticality safety computations provided the system being analyzed falls within the range of the experiments used in the validation.

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